E61 - Radiation Processing

SIGNIFICANCE AND USE
4.1 This guide is one of a set of guides and practices that provide recommendations for properly implementing dosimetry in radiation processing. In order to understand and effectively use this and other dosimetry standards, consider first “Practice for Dosimetry in Radiation Processing,” ASTM/ISO 52628, which describes the basic requirements that apply when making absorbed dose measurements in accordance with the ASTM E61 series of dosimetry standards. In addition, ASTM/ISO 52628 provides guidance on the selection of dosimetry systems and directs the user to other standards that provide information on individual dosimetry systems, calibration methods, uncertainty estimation and radiation processing applications.  
4.2 Radiation processing is carried out under fixed path conditions where (a) a process load is automatically moved through the radiation field by mechanical means or (b) a process load is irradiated statically by manually placing product at predetermined positions before the process is started. In both cases the process is controlled in such a manner that the process load position(s) and orientation(s) are reproducible within specified limits.
Note 2: Static irradiation encompasses irradiation of the process load using either manual rotation, no rotation or automated rotation.  
4.3 Some radiation processing facilities that utilize a fixed conveyor path for routine processing may also characterize a region within the radiation field for static radiation processing, sometimes referred to as “Off Carrier” processing.  
4.4 Many radiation processing applications require a minimum absorbed dose (to achieve a desired effect or to fulfill a legal requirement), and a maximum absorbed dose (to ensure that the product, material or substance still meets functional specifications or to fulfill a legal requirement).  
4.5 Information from the dose mapping is used to:  
4.5.1 Characterize the radiation process and assess the reproducibility of absorbed-dose va...
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1.1 This document provides guidance in determining absorbed-dose distributions (mapping) in products, materials or substances irradiated in gamma, X-ray (bremsstrahlung) and electron beam facilities.
Note 1: For irradiation of food and the radiation sterilization of health care products, specific ISO and ISO/ASTM standards containing dose mapping requirements exist. See ISO/ASTM Practices 51608, 51649, 51702 and 51818 and ISO 11137-1. Regarding the radiation sterilization of health care products, in those areas covered by ISO 11137-1, that standard takes precedence.  
1.2 This guide is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing. It is intended to be read in conjunction with ISO/ASTM 52628.  
1.3 Methods of analyzing the dose map data are described. Examples are provided of statistical methods that may be used to analyze dose map data.  
1.4 Dose mapping for bulk flow processing and fluid streams is not discussed.  
1.5 Dosimetry is an element of a total quality management system for an irradiation facility. Other controls besides dosimetry may be required for specific applications such as medical device sterilization and food preservation.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 The Fricke dosimetry system provides a reliable means for measurement of absorbed dose to water, based on a process of oxidation of ferrous ions to ferric ions in acidic aqueous solution by ionizing radiation (ICRU 80, PIRS-0815, (4)). In situations not requiring traceability to national standards, this system can be used for absolute determination of absorbed dose without calibration, as the radiation chemical yield of ferric ions is well characterized (see Appendix X3).  
4.2 The dosimeter is an air-saturated solution of ferrous sulfate or ferrous ammonium sulfate that indicates absorbed dose by an increase in optical absorbance at a specified wavelength. A temperature-controlled calibrated spectrophotometer is used to measure the absorbance.
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1.1 This practice covers the procedures for preparation, testing, and using the acidic aqueous ferrous ammonium sulfate solution dosimetry system to measure absorbed dose to water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. The system will be referred to as the Fricke dosimetry system. The Fricke dosimetry system may be used as either a reference standard dosimetry system or a routine dosimetry system.  
1.2 This practice is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for the Fricke dosimetry system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.  
1.3 The practice describes the spectrophotometric analysis procedures for the Fricke dosimetry system.  
1.4 This practice applies only to gamma radiation, X-radiation (bremsstrahlung), and high-energy electrons.  
1.5 This practice applies provided the following are satisfied:  
1.5.1 The absorbed dose range shall be from 20 Gy to 400 Gy (1).2  
1.5.2 The absorbed dose rate does not exceed 106 Gy·s−1 (2).  
1.5.3 For radioisotope gamma sources, the initial photon energy is greater than 0.6 MeV. For X-radiation (bremsstrahlung), the initial energy of the electrons used to produce the photons is equal to or greater than 2 MeV. For electron beams, the initial electron energy is greater than 8 MeV.  
Note 1: The lower energy limits given are appropriate for a cylindrical dosimeter ampoule of 12 mm diameter. Corrections for displacement effects and dose gradient across the ampoule may be required for electron beams (3). The Fricke dosimetry system may be used at lower energies by employing thinner (in the beam direction) dosimeter containers (see ICRU Report 35).  
1.5.4 The irradiation temperature of the dosimeter should be within the range of 10 °C to 60 °C.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 Blood and blood components are irradiated to predetermined absorbed doses to inactivate viable lymphocytes to help prevent transfusion-induced graft-versus-host disease (GVHD) in certain immunocompromised patients and those receiving related-donor products (1, 2).9  
4.2 The assurance that blood and blood components have been properly irradiated is of crucial importance for patient health. This shall be demonstrated by means of accurate absorbed-dose measurements on the product, or in simulated product.  
4.3 Blood and blood components are usually irradiated using gamma radiation from 137Cs or 60Co sources, or X-radiation from X-ray units.  
4.4 Blood irradiation specifications include a lower limit of absorbed dose, and may include an upper limit or central target dose. For a given application, any of these values may be prescribed by regulations that have been established on the basis of available scientific data (see 2.6).  
4.5 For each blood irradiator, an absorbed-dose rate at a reference position within the canister is measured as part of irradiator acceptance testing using a reference-standard dosimetry system. That reference-standard measurement is used to establish operating parameters so as to deliver specified dose to blood and blood components.  
4.6 Absorbed-dose measurements are performed within the blood or blood-equivalent volume for determining the absorbed-dose distribution. Such measurements are often performed using simulated product (for example, polystyrene is considered blood equivalent for 137Cs photon energies).  
4.7 Dosimetry is part of a measurement management system that is applied to ensure that the radiation process meets predetermined specifications (see ISO/ASTM Practice 52628).  
4.8 Blood and blood components are usually irradiated in chilled or frozen condition. Care should be taken, therefore, to ensure that the dosimeters and radiation-sensitive indicators can be used under such temperature conditions.  
4.9 Proper ...
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1.1 This practice outlines the irradiator installation qualification program and the dosimetric procedures to be followed during operational qualification and performance qualification of the irradiator. Procedures for the routine radiation processing of blood product (blood and blood components) are also given. If followed, these procedures will help ensure that blood product exposed to gamma radiation or X-radiation (bremsstrahlung) will receive absorbed doses with a specified range.  
1.2 This practice covers dosimetry for the irradiation of blood product for self-contained irradiators (free-standing irradiators) utilizing radionuclides such as 137Cs and  60Co, or X-radiation (bremsstrahlung). The absorbed dose range for blood irradiation is typically 15 Gy to 50 Gy.  
1.3 The photon energy range of X-radiation used for blood irradiation is typically from 40 keV to 300 keV.  
1.4 This practice also covers the use of radiation-sensitive indicators for the visual and qualitative indication that the product has been irradiated (see ISO/ASTM Guide 51539).  
1.5 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for dosimetry performed for blood irradiation. It is intended to be read in conjunction with ISO/ASTM Practice 52628.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides ...

SIGNIFICANCE AND USE
4.1 Various products and materials are routinely irradiated at pre-determined doses at electron beam facilities to preserve or modify their characteristics. Dosimetry requirements may vary depending on the radiation process and end use of the product. A partial list of processes where dosimetry may be used is given below.  
4.1.1 Polymerization of monomers and grafting of monomers onto polymers,  
4.1.2 Cross-linking or degradation of polymers,  
4.1.3 Curing of composite materials,  
4.1.4 Sterilization of health care products,  
4.1.5 Disinfection of consumer products,  
4.1.6 Food irradiation (parasite and pathogen control, insect disinfestation, and shelf-life extension),  
4.1.7 Control of pathogens and toxins in drinking water,  
4.1.8 Control of pathogens and toxins in liquid or solid waste,  
4.1.9 Modification of characteristics of semiconductor devices,  
4.1.10 Color enhancement of gemstones and other materials, and  
4.1.11 Research on radiation effects on materials.  
4.2 Dosimetry is used as a means of monitoring the irradiation process.
Note 2: Dosimetry with measurement traceability and known uncertainty is required for regulated radiation processes such as sterilization of health care products (see ISO 11137-1 and Refs (1-36)) and preservation of food (see ISO 14470 and Ref (4)). It may be less important for other processes, such as polymer modification, which may be evaluated by changes in the physical and chemical properties of the irradiated materials. Nevertheless, routine dosimetry may be used to monitor the reproducibility of the treatment process.
Note 3: Measured dose is often characterized as absorbed dose in water. Materials commonly found in single-use disposable medical devices and food are approximately equivalent to water in the absorption of ionizing radiation. Absorbed dose in materials other than water may be determined by applying conversion factors (5, 6).  
4.3 An irradiation process usually requires a minimum ab...
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1.1 This practice outlines dosimetric procedures to be followed in installation qualification (IQ), operational qualification (OQ) and performance qualifications (PQ), and routine processing at electron beam facilities.  
1.2 The electron beam energy range covered in this practice is between 300 keV and 25 MeV, although there are some discussions for other energies.  
1.3 Dosimetry is only one component of a total quality assurance program for adherence to good manufacturing practices used in radiation processing applications. Other measures besides dosimetry may be required for specific applications such as health care product sterilization and food preservation.  
1.4 Specific standards exist for the radiation sterilization of health care products and the irradiation of food. For the radiation sterilization of health care products, see ISO 11137-1 (Requirements) and ISO 11137-3 (Guidance on dosimetric aspects). For irradiation of food, see ISO 14470. In those areas covered by these standards, they take precedence. Information about effective or regulatory dose limits for food products is not within the scope of this practice (see ASTM Guides F1355, F1356, F1736, and F1885).  
1.5 This document is one of a set of standards that provides recommendations for properly implementing and utilizing dosimetry in radiation processing. It is intended to be read in conjunction with ISO/ASTM 52628, “Practice for Dosimetry in Radiation Processing”.
Note 1: For guidance in the calibration of routine dosimetry systems, see ISO/ASTM Practice 51261. For further guidance in the use of specific dosimetry systems, see relevant ISO/ASTM Practices. For discussion of radiation dosimetry for pulsed radiation, see ICRU Report 34.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and env...

SIGNIFICANCE AND USE
4.1 A variety of products and materials are irradiated with X-radiation to modify their characteristics and improve the economic value or to reduce their microbial population for health-related purposes. Dosimetry requirements might vary depending on the type and end use of the product. Some examples of irradiation applications where dosimetry may be used are:  
4.1.1 Sterilization of health care products;  
4.1.2 Treatment of food for the purpose of parasite and pathogen control, insect disinfestation, and shelf life extension;  
4.1.3 Disinfection of consumer products;  
4.1.4 Cross-linking or degradation of polymers and elastomers;  
4.1.5 Curing composite material;  
4.1.6 Polymerization of monomers and oligomer and grafting of monomers onto polymers;  
4.1.7 Enhancement of color in gemstones and other materials;  
4.1.8 Modification of characteristics of semiconductor devices; and  
4.1.9 Research on materials effects of irradiation.
Note 3: Dosimetry with measurement traceability and with known measurement uncertainty is required for regulated irradiation processes, such as the sterilization of health care products and treatment of food. Dosimetry may be less important for other industrial processes, such as polymer modification, which can be evaluated by changes in the physical properties of the irradiated materials. Nevertheless, routine dosimetry may be used to monitor the reproducibility of the radiation process.  
4.2 Radiation processing specifications usually include a pair of absorbed-dose limits: a minimum value to ensure the intended beneficial effect and a maximum value that the product can tolerate while still meeting its functional or regulatory specifications. For a given application, one or both of these values may be prescribed by process specifications or regulations. Knowledge of the dose distribution within irradiated material is essential to help meet these requirements. Dosimetry is essential to the radiation process since it i...
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1.1 This practice outlines the dosimetric procedures to be followed during installation qualification, operational qualification, performance qualification and routine processing at an X-ray (bremsstrahlung) irradiator. Other procedures related to operational qualification, performance qualification and routine processing that may influence absorbed dose in the product are also discussed.
Note 1: Dosimetry is only one component of a total quality assurance program for adherence to good manufacturing practices used in radiation processing applications.
Note 2: ISO/ASTM Practices 51649, 51818 and 51702 describe dosimetric procedures for electron beam and gamma facilities for radiation processing.  
1.2 For radiation sterilization of health care products, see ISO 11137-1, Sterilization of health care products – Radiation – Part 1: Requirements for development, validation and routine control of a sterilization process for medical devices. In those areas covered by ISO 11137-1, that standard takes precedence.  
1.3 For irradiation of food, see ISO 14470, Food irradiation – Requirements for development, validation and routine control of the process of irradiation using ionizing radiation for the treatment of food. In those areas covered by ISO 14470, that standard takes precedence.  
1.4 This document is one of a set of standards that provides recommendations for properly implementing and utilizing dosimetry in radiation processing. It is intended to be read in conjunction with ISO/ASTM Practice 52628, “Practice for Dosimetry in Radiation Processing”.  
1.5 In contrast to monoenergetic gamma radiation, the X-ray energy spectrum extends from low values (about 35 keV) up to the maximum energy of the electrons incident on the X-ray target (see Section 5 and Annex A1).  
1.6 Information about effective or regulatory dose limits and energy limits for X-ray applications is not within the scope of this practice.  
1.7 This ...

SIGNIFICANCE AND USE
4.1 Standards such as ISO 11137-1 (radiation sterilization of health care products) and ISO 14470 (irradiation of food) contain requirements that dosimetry used in the development, validation, and routine control of the process shall have measurement traceability to national or international standards and shall have a known level of uncertainty. The magnitude of the measurement uncertainty is important for assessing the results of the measurement system.  
4.1.1 This guide provides information on how to meet the fundamental requirement to determine a known level of uncertainty associated with a dose measurement, how to calculate the overall uncertainty, and how the uncertainty may differ depending on the application (e.g., OQ and PQ dose measurements, routine dose measurement, determination of minimum absorbed dose (Dmin) or maximum absorbed dose (Dmax) from the monitoring location dose (Dmon)). Information is provided on how to identify and calculate different components of uncertainty used to establish an uncertainty budget.  
4.2 Information on the range of achievable uncertainty values for specific dosimetry systems is given in the ISO/ASTM standards for the specific dosimetry systems. While the uncertainty values given in specific dosimetry standards are achievable, it should be noted that both smaller and larger uncertainty values might be obtained depending on measurement conditions and instrumentation. For more information, see also ISO/ASTM 52628.  
4.3 This guide uses the methodology adopted by the GUM for estimating uncertainties in measurements (see 2.4). Therefore, components of uncertainty are evaluated as either Type A uncertainty or Type B uncertainty.  
4.3.1 Quantifying individual components of uncertainty may assist the user in identifying actions to reduce the combined measurement uncertainty.  
4.4 Although this guide provides a framework for assessing uncertainty, it cannot substitute for critical thinking, intellectual honesty, and experi...
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1.1 This standard provides guidance on the use of concepts described in the JCGM (Joint Committee for Guides in Metrology) Evaluation of Measurement Data – Guide to the Expression of Uncertainty in Measurement (GUM) to estimate the uncertainties in the measurement of absorbed dose in radiation processing.  
1.2 Methods are given for identifying, evaluating, and estimating the components of measurement uncertainty associated with the use of dosimetry systems, and for calculating combined standard measurement uncertainty and expanded uncertainty of dose measurements based on the GUM methodology.  
1.3 Examples are given on how to develop a measurement uncertainty budget and a statement of uncertainty.  
1.3.1 Key components of uncertainty are derived as part of the derivation of the uncertainty budget. This standard identifies which components of uncertainty are carried forward as part of other analyses (e.g., assessment of process capability and process targets, and process variability), and which components from other standards are brought forward into this standard (e.g., precision of the dose measurement, calibration curve fit, and indirect measurement of dose).  
1.4 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and provides guidance for achieving compliance with the requirements of ISO 11137-1 (radiation sterilization of health care products), ISO 14470 (treatment of food), and ISO/ASTM 52628 related to the evaluation and documentation of the uncertainties associated with measurements made with a dosimetry system. It is intended to be read in conjunction with ISO/ASTM 52628 (Standard Practice for Dosimetry in Radiation Processing), and ISO/ASTM 51261 (Practice for Calibration of Routine Dosimetry Systems for Radiation Processing).  
1.5 To achieve compliance with the requirements of ISO 11137-1 (radiation sterilization of hea...

SIGNIFICANCE AND USE
4.1 The principal purpose of irradiation is to help ensure the safety of these foods for human consumption. Irradiation significantly reduces the numbers of pathogenic bacteria such as Campylobacter, Shiga toxin-Producing E coli, Listeria monocytogenes, Salmonella, Staphylococcus aureus, and Yersinia enterocolitica.
Note 3: Ionizing radiation doses below 10 kGy will reduce but may not eliminate spores of pathogenic bacteria including those of Clostridium botulinum, Clostridium perfringens, and Bacillus cereus.  
4.2 The process also inactivates parasites such as Trichinella spiralis and Toxoplasma gondii.  
4.3 The process may extend the shelf life of fresh meat and poultry by reducing the numbers of viable, spoilage bacteria, such as Pseudomonas species and lactic acid bacilli.  
4.4 Radiation processing of fresh, frozen, or processed meat and poultry is a critical control point (CCP) of a Hazard Analysis of Critical Control Points (HACCP) program. It serves as an important measure to control any residual risk from pathogenic microorganisms before the product reaches the consumer (4).  
4.5 The “Recommended International Code of Practice for Radiation Processing of Food” (CAC/RCP 19-1979) of the Codex Alimentarius identifies the essential practices to be implemented to achieve effective radiation processing of food, in general, in a manner that maintains quality and yields food products that are safe and suitable for consumption.
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1.1 This guide outlines procedures for the irradiation of fresh, frozen, or processed meat and poultry.
Note 1: The Codex Alimentarius Commission defines meat as “the edible part of any mammal” and poultry as “any domesticated bird, including chicken, turkeys, ducks, geese, guinea-fowls, or pigeons” (CAC/MISC 5).
Note 2: Current U.S. regulations limit the definition of meat and poultry as listed in 9 CFR Section 301.2 and 381.1, respectively. (2, 3).  
1.2 This guide covers the use of ionizing radiation to eliminate or reduce the numbers of vegetative, pathogenic microorganisms and parasites, and to extend the refrigerated shelf-life of those products by reducing the numbers of spoilage microorganisms in fresh, frozen, or processed meat and poultry. The absorbed dose for this application is typically less than 10 kGy.  
1.2.1 This guide covers gamma, electron beam, and X-radiation treatment.  
1.3 This guide addresses irradiation of pre-packaged product for retail sale or for use as an ingredient in other products. It also addresses the in-line irradiation of unpackaged product. Other specific ISO and ASTM standards exist for the irradiation of food. In those areas covered by ISO 14470, that standard takes precedence.  
1.4 This document is one of a set of standards that provides recommendations for properly implementing and utilizing radiation processing. It is intended to be read in conjunction with ISO/ASTM 52628.  
1.5 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 The alanine-EPR dosimetry system provides a means for measuring absorbed dose. It is based on the measurement of specific stable free radicals in crystalline alanine generated by ionizing radiation.  
4.2 Alanine-EPR dosimetry systems are used in reference- or transfer-standard or routine dosimetry systems in radiation applications that include: sterilization of medical devices and pharmaceuticals, food irradiation, polymer modifications, medical therapy and radiation damage studies in materials (1, 13-15).
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1.1 This practice covers dosimeter materials, instrumentation, and procedures for using the alanine-EPR dosimetry system to measure the absorbed dose in the photon or electron radiation processing of materials. The alanine system is based on electron paramagnetic resonance (EPR) spectroscopy of free radicals derived from the amino acid alanine.2  
1.2 The alanine dosimeter is classified as a type I dosimeter as it is affected by individual influence quantities in a well-defined way that can be expressed in terms of independent correction factors (see ISO/ASTM Practice 52628). The alanine dosimeter may be used in either a reference standard dosimetry system or in a routine dosimetry system.  
1.3 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM 52628 “Practice for Dosimetry in Radiation Processing” for alanine dosimetry system. It should be read in conjunction with ISO/ASTM 52628.  
1.4 This practice covers the use of alanine-EPR dosimetry systems under the following conditions:  
1.4.1 The absorbed dose range is between 0.001 kGy and 150 kGy.  
1.4.2 The absorbed dose rate is up to 1 × 102 Gy s-1 for continuous radiation fields and up to 3 × 1010 Gy s-1 for pulsed radiation fields (1-4).3  
1.4.3 The radiation energy for photons and electrons is between 0.1 MeV and 30 MeV (1, 2, 5-8).  
1.4.4 The irradiation temperature is between –78 °C and +70 °C (2, 9-12).  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 Various products and materials routinely are irradiated at predetermined doses in gamma irradiation facilities to reduce their microbial population or to modify their characteristics. Dosimetry requirements may vary depending upon the irradiation application and end use of the product. Some examples of irradiation applications where dosimetry may be used are:  
4.1.1 Sterilization of medical devices,  
4.1.2 Treatment of food for the purpose of parasite and pathogen control, insect disinfestation, and shelf life extension,  
4.1.3 Disinfection of consumer products,  
4.1.4 Cross-linking or degradation of polymers and elastomers,  
4.1.5 Polymerization of monomers and grafting of monomers onto polymers,  
4.1.6 Enhancement of color in gemstones and other materials,  
4.1.7 Modification of characteristics of semiconductor devices, and  
4.1.8 Research on materials effects.
Note 3: Dosimetry is required for regulated irradiation processes such as sterilization of medical devices and the treatment of food. It may be less important for other industrial processes, for example, polymer modification, which can be evaluated by changes in the physical and chemical properties of the irradiated materials.  
4.2 An irradiation process usually requires a minimum absorbed dose to achieve the intended effect. There also may be a maximum absorbed dose that the product can tolerate and still meet its functional or regulatory specifications. Dosimetry is essential to the irradiation process since it is used to determine both of these limits and to confirm that the product is routinely irradiated within these limits.  
4.3 The absorbed-dose distribution within the product depends on the overall product dimensions and mass, irradiation geometry, and source activity distribution.  
4.4 Before an irradiation facility can be used, it must be qualified to determine its effectiveness in reproducibly delivering known, controllable absorbed doses. This involves testing the pro...
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1.1 This practice outlines the installation qualification program for an irradiator and the dosimetric procedures to be followed during operational qualification, performance qualification, and routine processing in facilities that process products with ionizing radiation from radionuclide gamma sources to ensure that product has been treated within a predetermined range of absorbed dose. Other procedures related to operational qualification, performance qualification, and routine processing that may influence absorbed dose in the product are also discussed.
Note 1: Dosimetry is only one component of a total quality assurance program for adherence to good manufacturing practices used in radiation processing applications.
Note 2: ISO/ASTM Practices 51818 and 51649 describe dosimetric procedures for low and high enery electron beam facilities for radiation processing and ISO/ASTM Practice 51608 describes procedures for X-ray (bremsstrahlung) facilities for radiation processing.  
1.2 For the radiation sterilization of health care products, see ISO 11137-1. In those areas covered by ISO 11137-1, that standard takes precedence.  
1.3 This document is one of a set of standards that provides recommendations for properly implementing and utilizing dosimetry in radiation processing. It is intended to be read in conjunction with ASTM Practice E2628.  
1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization...

SIGNIFICANCE AND USE
4.1 The radiochromic film dosimetry system provides a means for measuring absorbed dose based on radiation-induced change in color using spectrophotometers, densitometers or scanned images.  
4.2 Radiochromic film dosimetry systems are commonly used in industrial radiation processing, for example in the sterilization of medical devices and the irradiation of foods.
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1.1 This is a practice for using radiochromic film dosimetry systems to measure absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose to water. Radiochromic film dosimetry systems are generally used as routine dosimetry systems.  
1.2 The radiochromic film dosimeter is classified as a type II dosimeter on the basis of the complex effect of influence quantities (see ISO/ASTM 52628).  
1.3 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM 52628 “Practice for Dosimetry in Radiation Processing” for a radiochromic film dosimetry system. It is intended to be read in conjunction with ISO/ASTM 52628.  
1.4 This practice covers the use of radiochromic film dosimetry systems under the following conditions:  
1.4.1 The absorbed dose range is 1 Gy to 150 kGy.  
1.4.2 The absorbed dose rate is 1 × 10-2 to 1 × 1013 Gy·s-1 (1-4).2  
1.4.3 The photon energy range is 0.1 to 50 MeV.  
1.4.4 The electron energy range is 70 keV to 50 MeV.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 In radiation processing, TLDs are mainly used in the irradiation of blood products (see ISO/ASTM Practice 51939) and insects for sterile insect release programs (see ISO/ASTM Guide 51940). TLDs may also be used in other radiation processing applications such as the sterilization of medical products, food irradiation, modification of polymers, irradiation of electronic devices, and curing of inks, coatings and adhesives. (See ISO/ASTM Practices 51608, 51649, and 51702.)  
4.2 For radiation processing, the absorbed-dose range of interest is from 1 Gy to 100 kGy. Some TLDs can be used in applications requiring much lower absorbed doses (for example, for personnel dosimetry), but such applications are outside the scope of this practice. Examples of TLDs and applicable dose ranges are given in Table 1. Information on various types of TLDs and their applications can be found in Refs (1-10).7 (A) This table is taken from Ref (6). Ranges are approximate, and may vary with batch. Supralinearity refers to a region where the slope of the response versus dose curve is greater than that for the linear region.  
4.3 Information on other dosimetry systems used for radiation processing can be found in ICRU Report 80.
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1.1 This practice covers procedures for the use of thermoluminescence dosimeters (TLDs) to measure the absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose to water. Thermoluminescence-dosimetry systems (TLD systems) are generally used as routine dosimetry systems.  
1.2 The thermoluminescence dosimeter (TLD) is classified as a type II dosimeter on the basis of the complex effect of influence quantities on the dosimeter response. See ISO/ASTM Practice 52628.  
1.3 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM 52628 “Practice for Dosimetry in Radiation Processing” for a TLD system. It is intended to be read in conjunction with ISO/ASTM 52628.  
1.4 This practice covers the use of TLD systems under the following conditions:  
1.4.1 The absorbed-dose range is from 1 Gy to 10 kGy.  
1.4.2 The absorbed-dose rate is between 1 × 10-2 and 1 × 1010 Gy s-1.  
1.4.3 The radiation-energy range for photons and electrons is from 0.1 to 50 MeV.  
1.5 This practice does not cover measurements of absorbed dose in materials subjected to neutron irradiation.  
1.6 This practice does not cover procedures for the use of TLDs for determining absorbed dose in radiation-hardness testing of electronic devices or for clinical dosimetry. Procedures for the use of TLDs for radiation-hardness testing are given in ASTM Practice E668. Procedures for use of TLDs in clinical dosimetry are given in ISO 28057.  
1.7 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.8 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 The CTA dosimetry system provides a means for measuring absorbed dose based on a change in optical absorbance in the CTA dosimeter following exposure to ionizing radiation (2-10).  
4.2 CTA dosimetry systems are commonly used in industrial radiation processing, for example in the modification of polymers and sterilization of health care products.  
4.3 CTA dosimeter film can be particularly useful in absorbed dose mapping because it is available in a reel of 100 m whereby the user can cut any length of strip for use. When the CTA film is measured using a strip measurement device with a narrow distance interval (for example, 2 mm), it can provide high resolution results in a linear direction.  
4.4 CTA is used to measure relative dose such as depth dose profiles in electron beam and reference phantom tests to assess irradiator changes in gamma.  
4.5 When CTA is used as a routine monitoring dosimeter the user must take into consideration the effects of the multiple influence quantities that can affect the result and use appropriate techniques, as discussed herein, for characterizing and mitigating such influences and understanding their contribution to measurement uncertainty. Without such effort the dosimetry system may not meet the user’s requirements for dosimetric release of some types of products (for example, health care products).
SCOPE
1.1 This is a practice for using a cellulose triacetate (CTA) dosimetry system to measure absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose to water. CTA is used as a routine dosimetry system or used for relative dose measurements (that is, non-traceable dose measurements).  
1.2 The CTA dosimeter is classified as a type II dosimeter on the basis of the complex effect of influence quantities on its response (see ISO/ASTM Practice 52628).  
1.3 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM 52628 “Practice for Dosimetry in Radiation Processing” for a CTA dosimetry system. It is intended to be read in conjunction with ISO/ASTM 52628.  
1.4 This practice covers the use of CTA dosimetry systems under the following conditions:  
1.4.1 The absorbed dose range is 10 kGy to 300 kGy.
Note 1: The dosimeter film irradiated to doses exceeding 200 kGy becomes brittle to some degree and must be handled with care. This may limit the practical dose range depending on the type of testing and handling required.  
1.4.2 The absorbed-dose rate range is 3 Gy/s to 4 ×1010 Gy·s (1).2  
1.4.3 The photon energy range is 0.1 to 50 MeV.  
1.4.4 The electron energy range is 0.2 to 50 MeV.  
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 The dichromate system provides a reliable means for measuring absorbed dose to water. It is based on a process of reduction of dichromate ions to chromic ions in acidic aqueous solution by ionizing radiation.  
4.2 The dosimeter is a solution containing silver and dichromate ions in perchloric acid in an appropriate container such as a sealed glass ampoule. The solution indicates absorbed dose by a change (decrease) in optical absorbance at a specified wavelength(s) ((3), ICRU Report 80). A calibrated spectrophotometer is used to measure the absorbance.
SCOPE
1.1 This practice covers the preparation, testing, and procedure for using the acidic aqueous silver dichromate dosimetry system to measure absorbed dose to water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the system will be referred to as the dichromate system. The dichromate dosimeter is classified as a type I dosimeter on the basis of the effect of influence quantities. The dichromate system may be used as either a reference standard dosimetry system or a routine dosimetry system.  
1.2 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for the dichromate dosimetry system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.  
1.3 This practice describes the spectrophotometric analysis procedures for the dichromate system.  
1.4 This practice applies only to gamma radiation, X-radiation/bremsstrahlung, and high energy electrons.  
1.5 This practice applies provided the following conditions are satisfied:  
1.5.1 The absorbed dose range is from 2 × 10 3 to 5 × 104 Gy.  
1.5.2 The absorbed dose rate does not exceed 600 Gy/pulse (12.5 pulses per second), or does not exceed an equivalent dose rate of 7.5 kGy/s from continuous sources (1).2  
1.5.3 For radionuclide gamma sources, the initial photon energy shall be greater than 0.6 MeV. For bremsstrahlung photons, the initial energy of the electrons used to produce the bremsstrahlung photons shall be equal to or greater than 2 MeV. For electron beams, the initial electron energy shall be greater than 8 MeV.  
Note 1: The lower energy limits given are appropriate for a cylindrical dosimeter ampoule of 12 mm diameter. Corrections for displacement effects and dose gradient across the ampoule may be required for electron beams (2). The dichromate system may be used at lower energies by employing thinner (in the beam direction) dosimeter containers (see ICRU Report 35).  
1.5.4 The irradiation temperature of the dosimeter shall be above 0 °C and should be below 80 °C.  
Note 2: The temperature coefficient of dosimeter response is known only in the range of 5 to 50 °C (see 5.2). Use outside this range requires determination of the temperature coefficient.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. Specific precautionary statements are given in 9.3.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 Operational qualification (OQ) will be used to demonstrate that the irradiator, as installed, is capable of operating and delivering dose to product being irradiated with defined acceptance criteria by determining dose distribution and magnitude through dose mapping exercises and relating these distributions to process parameters.  
4.2 The principle objectives of OQ are to:  
4.2.1 Establish the dose distribution and create a baseline PQ grid for mapping actual product,  
4.2.2 Establish the relationship for dose uniformity ratio (DUR) as a function of density,  
4.2.3 Establish the relationship for cycle time (CT) as a function of density and source activity, and  
4.2.4 Establish the relationship for minimum dose (kGy) as a function of density, cycle time and source activity.  
4.3 OQ exercises could augment or replace PQ exercises. It is the facility’s responsibility to document the rationale when using OQ data for PQ purposes.  
4.4 A design of experiments approach may help rationalize the types of OQ tests needed. For some irradiator changes, the minimum number of densities may be different depending on the degree of anticipated change in dose distribution. These decisions should be covered through a documented change control process. See ISO/ASTM 52701.  
4.5 This guide is not intended to address OQ requirements in research or experimental irradiators.  
4.6 An irradiation facility is able to process different process load configurations. For example, an irradiation container may be designed to accommodate boxes, sacks and drums. It is important to consider OQ studies that characterize the irradiator for different irradiation geometries.  
4.7 The bulk density, dimensions and atomic composition are important properties in dose mapping. See Appendix X2 for examples of materials for potential use in OQ studies.
SCOPE
1.1 This document provides guidance on operational qualification (OQ) tests to meet the OQ requirements defined in ISO 11137-1, ISO 14470, ISO/ASTM 51702, and ISO/ASTM 52303 for gamma irradiators.  
1.1.1 The types of OQ tests are discussed to help the user gain an increased understanding of operational aspects of their irradiator and determine which OQ tests are appropriate for the assessment of irradiator change.  
1.1.2 The facility should assess the rationale for the OQ tests chosen and for the ones that have been deemed to be unnecessary.  
1.2 Specific requirements for OQ are dependent on the application of the irradiation process and are not within the scope of this guide. For example, requirements for OQ when sterilizing healthcare products can be found in ISO 11137-1.  
1.3 A change to the irradiator is a component of the change control process. The OQ testing following the irradiator change is determined as part of the change control documentation and should include rationale to support decision(s) on which tests are required to be completed.  
1.4 For an OQ study following an irradiator change, the required OQ tests are defined procedurally with established acceptance criteria. (The OQ tests in the appendixes have examples of defined acceptance criteria with a rationale for the acceptance.) When multiple tests are used in the assessment of change, no individual OQ test should be solely relied upon; rather, the composite of OQ test results should be used to help provide a clear justification for the conclusion regarding irradiator change.  
1.5 Many calculations in this guide were completed using Microsoft Excel (for example, ANOVA, t-test, p-value), but numerous other software tools are commercially available.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard...

SIGNIFICANCE AND USE
4.1 Absorbed doses of or below 1 kGy can inactivate some parasites, such as the broad fish tapeworm (Dibothrocephalus latus) (2).  
4.2 Absorbed doses below 10 kGy can reduce or eliminate vegetative cells of pathogenic sporeforming and non-sporeforming microorganisms, such as Clostridium spp., Vibrio spp., Salmonellae, Listeria monocytogenes, or Staphylococcus aureus, that may be present in fresh or frozen product.  
4.2.1 Absorbed doses below 10 kGy can reduce the numbers of some spores, but are not adequate to reduce the potential health risk from microbial spores or toxins (3).  
4.3 Absorbed doses below 10 kGy can reduce or eliminate the vegetative cells of sporeforming and non-sporeforming microorganisms, such as Bacillus or Pseudomonas species, that cause spoilage of fresh product, thus extending refrigerated shelf life in many cases (4).
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1.1 This guide outlines procedures and operations for the irradiation of raw, untreated, fresh (chilled), or frozen finfish and aquatic invertebrates, while ensuring that the irradiated product is safe and wholesome.  
1.1.1 Aquatic invertebrates include mollusks, crustacea, echinoderms, etc.
1.1.1.1 Mollusks include bivalve shellfish, such as clams, mussels, and oysters; snails; and cephalopods, such as squid and octopus.
1.1.1.2 Crustacea include shellfish such as shrimp, lobster, crabs, prawns and crayfish.
1.1.1.3 Echinoderms include sea urchins and sea cucumbers.  
1.2 This guide covers absorbed doses used to reduce the microbial and parasite populations in aquatic invertebrates and finfish. Such doses typically are below 10 kGy (1).2  
1.2.1 This guide covers gamma, electron beam, and X-radiation treatment.  
1.3 The use of reduced-oxygen packaging (vacuum or modified atmosphere, and including products packed in oil) with irradiated, raw product is not covered by this guide. The anaerobic environment created by reduced-oxygen packaging provides the potential for outgrowth of, and toxin production from, Clostridium botulinum spores.  
1.4 This guide does not cover the irradiation of smoked or dried fish to reduce microbial load or to control insect infestation.  
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.6 This document is one of a set of standards that provides recommendations for properly implementing and utilizing radiation processing. It is intended to be read in conjunction with ISO/ASTM Practice 52628.  
1.7 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.8 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 Use as an Analytical Tool—Mathematical methods provide an analytical tool to be employed for many applications related to absorbed dose determinations in radiation processing. Mathematical calculations may not be used as a substitute for routine dosimetry in some applications (for example, medical device sterilization, food irradiation).  
4.2 Dose Calculation—Absorbed-dose calculations may be performed for a variety of photon/electron environments and irradiator geometries.  
4.3 Evaluate Process Effectiveness—Mathematical models may be used to evaluate the impact of changes in product composition, loading configuration, and irradiator design on dose distribution.  
4.4 Complement or Supplement to Dosimetry—Dose calculations may be used to establish a detailed understanding of dose distribution, providing a spatial resolution not obtainable through measurement. Calculations may be used to reduce the number of dosimeters required to characterize a procedure or process (for example, dose mapping).  
4.5 Alternative to Dosimetry—Dose calculations may be used when dosimetry is impractical (for example, granular materials, materials with complex geometries, material contained in a package where dosimetry is not practical or possible).  
4.6 Facility Design—Dose calculations are often used in the design of a new irradiator and can be used to help optimize dose distribution in an existing facility or radiation process. The use of modeling in irradiator design can be found in Refs (2-7).  
4.7 Validation—The validation of the model should be done through comparison with reliable and traceable dosimetric measurements. The purpose of validation is to demonstrate that the mathematical method makes reliable predictions of dose and other transport quantities. Validation compares predictions or theory to the results of an appropriate experiment. The degree of validation is commensurate with the application. Guidance is given in the documents referenced in Annex A2.  
...
SCOPE
1.1 This guide describes different mathematical methods that may be used to calculate absorbed dose and criteria for their selection. Absorbed-dose calculations can determine the effectiveness of the radiation process, estimate the absorbed-dose distribution in product, or supplement or complement, or both, the measurement of absorbed dose.  
1.2 Radiation processing is an evolving field and annotated examples are provided in Annex A6 to illustrate the applications where mathematical methods have been successfully applied. While not limited by the applications cited in these examples, applications specific to neutron transport, radiation therapy and shielding design are not addressed in this document.  
1.3 This guide covers the calculation of radiation transport of electrons and photons with energies up to 25 MeV.  
1.4 The mathematical methods described include Monte Carlo, point kernel, discrete ordinate, semi-empirical and empirical methods.  
1.5 This guide is limited to the use of general purpose software packages for the calculation of the transport of charged or uncharged particles and photons, or both, from various types of sources of ionizing radiation. This standard is limited to the use of these software packages or other mathematical methods for the determination of spatial dose distributions for photons emitted following the decay of 137Cs or 60Co, for energetic electrons from particle accelerators, or for X-rays generated by electron accelerators.  
1.6 This guide assists the user in determining if mathematical methods are a useful tool. This guide may assist the user in selecting an appropriate method for calculating absorbed dose. The user must determine whether any of these mathematical methods are appropriate for the solution to their specific application and what, if any, software to apply.
Note 1: The user is urged to apply these predictive techniques while being aware of the need for experien...

SIGNIFICANCE AND USE
4.1 The judicious selection of a contact material is part of Good Manufacturing Practices (GMPs) for the irradiation of prepackaged foods. This guide recognizes the need to evaluate the impact of packaging materials on the safety and quality of foods irradiated to control the proliferation of food-borne pathogens, as well as their impact on foods irradiated for other purposes, such as for phytosanitary treatment, delay of ripening, or shelf-life extension.  
4.2 As part of the evaluation, the selection process should consider the effects of irradiation on the chemical and physical properties of the contact material.  
4.3 Packaging is not considered to be a food preservation technique for overcoming any deficiencies attributable to inadequate GMPs during preparation, storage, or treatment of foods to be irradiated. The quality of the irradiated food will depend heavily on its initial quality, control of the irradiation process, storage temperature and handling of the food after irradiation.
SCOPE
1.1 This guide provides a format to assist producers in selecting food contact materials that have the desirable characteristics for their intended use and that comply with applicable standards or government authorizations. It outlines parameters that should be considered when selecting food contact materials intended for use during irradiation of prepackaged foods and it examines the criteria for fitness for their use.  
1.2 This guide identifies known regulations and regulatory frameworks worldwide pertaining to food contact materials for holding foods during irradiation, but it does not address all regulatory issues associated with the selection and use of packaging materials for foods to be irradiated. It is the responsibility of the user of this guide to determine the pertinent regulatory issues in each country where foods are to be irradiated and where irradiated foods are distributed.  
1.3 This guide does not address all of the food safety issues associated with the synergistic effects of irradiation and packaging as food preservation techniques on the extension of shelf life or food quality. It is the responsibility of the user of this guide to determine the critical food safety issues and to conduct appropriate product assessment tests to determine the compatibility between the packaging application and irradiation relative to changes in sensory attributes and shelf life.  
1.4 This guide does not address the use of irradiation as a processing aid for the production or sterilization of food packaging materials.  
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.6 This document is one of a set of standards that provides recommendations for properly implementing and utilizing radiation processing. It is intended to be read in conjunction with ISO/ASTM 52628.  
1.7 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.8 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 Control charts are the primary process monitoring tool in SPC for radiation processing. The general objectives of implementing a SPC program with control charts are to:  
4.1.1 Increase knowledge of the process,  
4.1.2 Control the process to provide a targeted or required process output,  
4.1.3 Reduce variation of the process output or in other ways improve the performance of a process, and  
4.1.4 Identify single process run results that are outside of established control limits but may be within the USL and LSL limits.  
4.2 These objectives when achieved:  
4.2.1 Reduce costs through reduction of losses due to scrap, rework, and investigation time,  
4.2.2 Improve consistency of the process output,  
4.2.3 Facilitate preventive process adjustments, and  
4.2.4 Provide evidence of accurate process targeting and process performance; state of statistical control.
SCOPE
1.1 This document provides guidance for the statistical analysis of the irradiation process from dosimetric data.  
1.2 This document is one of a set of guides and practices that provide recommendations for properly implementing dosimetry in radiation processing. It is intended to be read in conjunction with ISO/ASTM 52628 and ISO/ASTM 52303.  
1.3 This document employs a set of standard statistical methods and is intended to be read in conjunction with Practice E2586, Practice E2281, Practice E2587, and ASTM Manual MNL72.  
1.4 This guide is applicable to high-energy electron beam, X-ray and gamma-ray irradiation processes.  
1.5 This document assumes user knowledge of statistics, radiation processing, and radiation dosimetry. (See Annex A6)  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 The radiochromic optical waveguide dosimetry system provides a means of measuring absorbed dose in materials. Under the influence of ionizing radiation such as photons, chemical reactions take place in the radiochromic optical waveguide creating and/or modifying optical absorbance bands in the visible region of the spectrum. Optical response is determined at selected wavelengths using the equations in 3.1.4. Examples of appropriate wavelengths for the analysis for specific dosimetry systems are provided by their manufacturers and in Refs (1-5).  
4.2 These dosimetry systems commonly are applied in the industrial radiation processing of a variety of products, for example, the sterilization of medical devices and radiation processing of foods (4-6).
Note 1: For additional information on dosimetry systems used in radiation processing, see ICRU Report 80.
SCOPE
1.1 This is a practice for using a radiochromic optical waveguide dosimetry system to measure absorbed dose in materials irradiated by photons and high energy electrons in terms of absorbed dose to water. The radiochromic optical waveguide dosimetry system is generally used as a routine dosimetry system.  
1.2 The optical waveguide dosimeter is classified as a Type II dosimeter on the basis of the complex effect of influence quantities (see ISO/ASTM Practice 52628).  
1.3 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM 52628 for an optical waveguide dosimetry system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.  
1.4 This practice applies to radiochromic optical waveguide dosimeters that can be used within part or all of the specified ranges as follows:  
1.4.1 The absorbed dose range is from 1 Gy to 20 000 Gy.  
1.4.2 The absorbed dose rate is from 0.001 Gy/s to 1000 Gy/s.  
1.4.3 The radiation photon energy range is from 1 MeV to 10 MeV.  
1.4.4 The radiation electron energy range is from 3 MeV to 25 MeV.  
1.4.5 The irradiation temperature range is from –78 °C to +60 °C.  
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 Ionizing radiation produces physical or chemical changes in many materials that can be measured and related to absorbed dose. Materials with radiation-induced changes that have been thoroughly studied can be used as dosimeters in radiation processing.  
Note 3: The scientific basis for commonly used dosimetry systems and detailed descriptions of the radiation-induced interactions are given in ICRU Report 80.  
4.2 Before a material can be considered for use as a dosimeter, certain characteristics related to manufacture and measurement of its response to ionizing radiation need to be considered, including:  
4.2.1 the ability to manufacture batches of the material with evidence demonstrating a reproducible radiation-induced change,  
4.2.2 the availability of instrumentation for measuring this change, and  
4.2.3 the ability to take into account effects of influence quantities on the dosimeter response and on the measured absorbed-dose values.  
4.3 Dosimeter/dosimetry system characterization is conducted to determine the performance characteristics for a dosimeter/dosimetry system related to its capability for measuring absorbed dose. The information obtained from dosimeter/dosimetry system characterization includes the reproducibility of the measured absorbed-dose value, the useful absorbed-dose range, effects of influence quantities, and the conditions under which the dosimeters can be calibrated and used effectively.
Note 4: When dosimetry systems are calibrated under the conditions of use, effects of influence quantities may be minimized or eliminated, because the effects can be accounted for or incorporated into the calibration method (see ISO/ASTM Practice 51261).  
4.4 The influence quantities of importance might differ for different radiation processing applications and facilities. For references to standards describing different applications and facilities, see ISO/ASTM Practice 52628.  
4.5 Classification of a dosimeter as a type I dosimeter ...
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1.1 This guide provides guidance on determining the performance characteristics of dosimeters and dosimetry systems used in radiation processing.  
1.2 This guide describes the influence quantities that might affect the performance of dosimeters and dosimetry systems and that should be considered during dosimeter/dosimetry system characterization.  
1.3 Users of this guide are directed to existing standards and literature for procedures to determine the effects from individual influence quantities and from combinations of more than one influence quantity.  
1.4 Guidance is provided regarding the roles of the manufacturers, suppliers, and users in the characterization of dosimeters and dosimetry systems.  
1.5 This guide does not address how the dosimeter/dosimetry system characterization information is to be used in radiation processing applications or in the calibration of dosimetry systems.
Note 1: For guidance on the use of dosimeter/dosimetry system characterization information for the selection and use of a dosimetry system, the user is directed to ISO/ASTM Practice 52628.
Note 2: For guidance on the use of dosimeter/dosimetry system characterization information for dosimetry system calibration, the user is directed to ISO/ASTM Practice 51261.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 Ionizing radiation is used to produce various desired effects in products. Examples of applications include the sterilization of medical products, microbial reduction, modification of polymers and electronic devices, and curing of inks, coatings, and adhesives (4).  
4.2 Absorbed-dose measurements, with statistical controls and documentation, are necessary to ensure that products receive the desired absorbed dose. These controls include a program that addresses requirements for calibration of routine dosimetry system.  
4.3 A routine dosimetry system calibration procedure as described in this document provides the user with a dosimetry system whose dose measurements are traceable to national or international standards for the conditions of use (see Annex A4). The dosimetry system calibration is part of the user’s measurement management system.
SCOPE
1.1 This practice specifies the requirements for calibrating routine dosimetry systems for use in radiation processing, including establishing measurement traceability and estimating uncertainty in the measured dose using the calibrated dosimetry system.
Note 1: Regulations or other directives exist in many countries that govern certain radiation processing applications such as sterilization of healthcare products and radiation processing of food requiring that absorbed-dose measurements be traceable to national or international standards (ISO 11137-1, Refs (1-3)2).  
1.2 The absorbed-dose range covered is up to 1 MGy.  
1.3 The radiation types covered are photons and electrons with energies from 80 keV to 25 MeV.  
1.4 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ASTM E2628 “Practice for Dosimetry in Radiation Processing” for the calibration of routine dosimetry systems. It is intended to be read in conjunction with ASTM E2628 and the relevant ASTM or ISO/ASTM standard practice for the dosimetry system being calibrated referenced in Section 2.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 The design and operation of a self-contained irradiator should ensure that reproducible absorbed doses are obtained when the same irradiation parameters are used. Dosimetry is performed to determine the relationship between the irradiation parameters and the absorbed dose.  
4.1.1 For most applications, the absorbed dose is expressed as absorbed dose to water (see ISO/ASTM Practice 51261). For conversion of absorbed dose to water to that to other materials, for example, silicon, see Annex A1 of ISO/ASTM Practice 51261.  
4.2 Self-contained dry-storage gamma irradiators contain properly shielded radioactive sources, namely  137Cs or  60Co, that emit ionizing electromagnetic radiation (gamma radiation). These irradiators have an enclosed, accessible irradiator sample chamber connected with a sample positioning system, for example, irradiator drawer, rotor, or irradiator turntable, as part of the irradiation device.  
4.3 Self-contained dry-storage gamma irradiators can be used for many radiation processing applications, including the calibration irradiation of dosimeters; studies of dosimeter influence quantities; radiation effects studies, and irradiation of materials or biological samples for process compatibility studies; batch irradiations of microbiological, botanical, or in-vitro samples; irradiation of small animals; radiation “hardness” testing of electronics components and other materials; and batch radiation processing of containers of samples.
Note 1: Self-contained dry-storage gamma irradiators contain a sealed radiation source, or an array of sealed radiation sources securely held in a dry container constructed of solid materials. The sealed radiation sources are shielded at all times, and human access to the chamber undergoing irradiation is not physically possible due to the irradiator’s design configuration (see ANSI/HPS N43.7).
Note 2: For reference–standard dosimetry, the absorbed dose and absorbed-dose rate can be expressed in water or o...
SCOPE
1.1 This practice outlines dosimetric procedures to be followed with self-contained dry-storage gamma irradiators. For irradiators used for routine processing, procedures are given to ensure that product processed will receive absorbed doses within prescribed limits.  
1.2 This practice covers dosimetry in the use of dry-storage gamma irradiators, namely self-contained dry-storage 137Cs or  60Co irradiators (shielded freestanding irradiators). It does not cover underwater pool sources, panoramic gamma sources, nor does it cover self-contained bremsstrahlung X-ray units.  
1.3 The absorbed-dose range for the use of the dry-storage self-contained gamma irradiators covered by this practice is typically 1 to 105 Gy, depending on the application. The absorbed-dose rate range typically is from 10–2 to 103 Gy/min.  
1.4 For irradiators supplied for specific applications, specific ISO/ASTM or ASTM practices and guides provide dosimetric procedures for the application. For procedures specific to dosimetry in blood irradiation, see ISO/ASTM Practice 51939. For procedures specific to dosimetry in radiation research on food and agricultural products, see ISO/ASTM Practice 51900 . For procedures specific to radiation hardness testing, see ASTM Practice E1249. For procedures specific to the dosimetry in the irradiation of insects for sterile release programs, see ISO/ASTM Guide 51940. In those cases covered by ISO/ASTM 51939, 51900 , 51940, or ASTM E1249, those standards take precedence.  
1.5 This document is one of a set of standards that provides recommendations for properly implementing and utilizing dosimetry in radiation processing. It is intended to be read in conjunction with ASTM E2628, “Practice for Dosimetry in Radiation Processing”.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate ...

SIGNIFICANCE AND USE
4.1 Radiation processing of articles in both commercial and research applications may be carried out for a number of purposes. These include, for example, sterilization of health care products, reduction of the microbial populations in foods and modification of polymers. The radiations used may be accelerated electrons, gamma-radiation from radionuclide sources such as cobalt-60, or X-radiation.  
4.2 To demonstrate control of radiation processes that are dependent on the delivery of a known dose, the absorbed dose must be measured using a dosimetry system, the calibration of which, is traceable to appropriate national or international standards. The radiation-induced change in the dosimeter is evaluated and related to absorbed dose through calibration. Dose measurements required for particular processes are described in other standards referenced in this practice.
SCOPE
1.1 This practice describes the basic requirements that apply when making absorbed dose measurements in accordance with the ASTM E61 series of dosimetry standards. In addition, it provides guidance on the selection of dosimetry systems and directs the user to other standards that provide specific information on individual dosimetry systems, calibration methods, uncertainty estimation and radiation processing applications.  
1.2 This practice applies to dosimetry for radiation processing applications using electrons or photons (gamma- or X-radiation).  
1.3 This practice addresses the minimum requirements of a measurement management system, but does not include general quality system requirements.  
1.4 This practice does not address personnel dosimetry or medical dosimetry.  
1.5 This practice does not apply to primary standard dosimetry systems.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 The purpose of radiation treatment, as discussed in this guide, is to minimize the pest risk and to maximize the safety associated with the movement and use of fresh agricultural produce.  
4.2 Irradiation as a phytosanitary treatment can prevent development or emergence of the adult stage where adults are not present in the agricultural produce (for example, fruit flies) or sterilize the adult where that stage is present (for example, weevils). (4)
SCOPE
1.1 This guide provides procedures for the radiation processing of fresh agricultural produce, for example, fruits, vegetables, and cut flowers, as a phytosanitary treatment. This guide is directed primarily toward the treatment needed to control regulated pests commonly associated with fresh agricultural produce.  
1.2 This guide covers gamma, electron beam and X-radiation treatment.  
1.3 The typical absorbed dose range used for phytosanitary treatments is between 60 gray (Gy) and 600 gray (Gy). The practical minimum or maximum dose of a treatment may be higher or lower than this range, depending on the type of pest to be controlled and the radiation tolerance of a particular type of produce. If the minimum effective dose necessary to achieve the desired phytosanitary effect is greater than the radiation tolerance of the produce, then irradiation is not an appropriate treatment (see 5.2).  
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.5 This document is one of a set of standards that provides recommendations for properly implementing and utilizing radiation processing. It is intended to be read in conjunction with ISO/ASTM Practice 52628.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 This practice is applicable to the use of calorimetric dosimetry systems for the measurement of absorbed dose in electron beams, the qualification of electron irradiation facilities, periodic checks of operating parameters of electron irradiation facilities, and calibration of other dosimetry systems in electron beams. Calorimetric dosimetry systems are most suitable for dose measurement at electron irradiation facilities utilizing conveyor systems for transport of product during irradiation.
Note 1: For additional information on calorimetric dosimetry system operation and use, see ICRU Report 80. For additional information on the use of dosimetry in electron accelerator facilities, see ISO/ASTM 51649, and ICRU Reports 34 and 35, and Refs (1-3).6  
4.2 The calorimetric dosimetry systems described in this practice are not primary standard dosimetry systems. The calorimeters are classified as Type II dosimeters (ISO/ASTM 52628). They might be used as internal standards at an electron beam irradiation facility, including being used as transfer standard dosimetry systems for calibration of other dosimetry systems, or they might be used as routine dosimeters. The calorimetric dosimetry systems are calibrated by comparison with transfer standard dosimeters.  
4.3 The dose measurement is based on the measurement of the temperature rise (dosimeter response) in an absorber (calorimetric body) irradiated by an electron beam. Different absorbing materials are used, but the response is usually defined in terms of dose to water.
Note 2: The calorimetric bodies of the calorimeters described in this practice are made from low atomic number materials. The electron fluences within these calorimetric bodies are almost independent of energy when irradiated with electron beams of 1.5 MeV or higher, and the mass collision stopping powers are approximately the same for these materials.  
4.4 The absorbed dose in other materials irradiated under equivalent conditions can be cal...
SCOPE
1.1 This practice covers the preparation and use of semi-adiabatic calorimetric dosimetry systems for measurement of absorbed dose and for calibration of routine dosimetry systems when irradiated with electrons for radiation processing applications. The calorimeters are either transported by a conveyor past a scanned electron beam or are stationary in a broadened beam.  
1.2 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for a calorimetric dosimetry system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.  
1.3 The calorimeters described in this practice are classified as Type II dosimeters on the basis of the complex effect of influence quantities. See ISO/ASTM Practice 52628.  
1.4 This practice applies to electron beams in the energy range from 1.5 to 12 MeV.  
1.5 The absorbed dose range depends on the calorimetric absorbing material and the irradiation and measurement conditions. Minimum dose is approximately 100 Gy and maximum dose is approximately 50 kGy.  
1.6 The average absorbed-dose rate range shall generally be greater than 10 Gy·s-1.  
1.7 The temperature range for use of these calorimetric dosimetry systems depends on the thermal resistance of the calorimetric materials, on the calibration range of the temperature sensor, and on the sensitivity of the measurement device.  
1.8 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.9 This international standard was developed in accordance with internationally recognized principles on standardization establis...

SIGNIFICANCE AND USE
4.1 A variety of irradiation processes use low energy electron beam facilities to modify product characteristics. Dosimetry requirements, the number and frequency of measurements, and record keeping requirements will vary depending on the type and end use of the products being processed. Dosimetry is often used in conjunction with physical, chemical, or biological testing of the product, to help verify specific treatment parameters.
Note 2: In many cases dosimetry results can be related to other quantitative product properties; for example, gel fraction, melt flow, elastic modulus, molecular weight distribution, or degree of cure.  
4.2 Radiation processing specifications usually include a minimum or maximum absorbed dose limit, or both. For a given application these limits may be set by government regulation or by limits inherent to the product itself.  
4.3 Critical operating parameters must be controlled to obtain reproducible dose distribution in processed materials. The electron beam energy, beam current, beam width and process line speed (conveying speed) affect absorbed dose.  
4.4 Before any electron beam facility can be routinely utilized, it must be characterized to determine the relationship between dose to product and the main operating parameters. This involves testing of the process equipment, calibrating the measuring instruments and the dosimetry system, and demonstrating the ability to consistently deliver the required dose within predetermined specifications.  
4.5 In order to establish metrological traceability for a dosimetry system and to measure doses with a known level of uncertainty, it is necessary to calibrate the dosimetry system under irradiation conditions that are consistent with those encountered in routine use. For example, a dosimetry system calibration conducted using penetrating gamma radiation or high energy electrons may result in significant dose measurement errors when the dosimetry system is used at low energy electron b...
SCOPE
1.1 This practice covers dosimetric procedures to be followed in installation qualification, operational qualification and performance qualification (IQ, OQ, PQ), and routine processing at electron beam facilities to ensure that the product has been treated with an acceptable range of absorbed doses. Other procedures related to IQ, OQ, PQ, and routine product processing that may influence absorbed dose in the product are also discussed.  
1.2 The electron beam energy range covered in this practice is between 80 and 300 keV, generally referred to as low energy.  
1.3 Dosimetry is only one component of a total quality assurance program for an irradiation facility. Other measures may be required for specific applications such as medical device sterilization and food preservation.  
1.4 Other specific ISO and ASTM standards exist for the irradiation of food and the radiation sterilization of health care products. For the radiation sterilization of health care products, see ISO 11137-1. In those areas covered by ISO 11137-1, that standard takes precedence. For food irradiation, see ISO 14470. Information about effective or regulatory dose limits for food products is not within the scope of this practice (see ASTM F1355 and F1356).  
1.5 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM 52628. It is intended to be read in conjunction with ISO/ASTM 52628.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on s...

SIGNIFICANCE AND USE
4.1 The PMMA dosimetry system provides a means for measuring absorbed dose based on a change in optical absorbance.  
4.2 PMMA dosimetry systems are commonly used in industrial radiation processing, for example in the sterilization of medical devices and the irradiation of foods.
SCOPE
1.1 This is a practice for using polymethylmethacrylate (PMMA) dosimetry systems to measure absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose to water. The PMMA dosimetry system is generally used as a routine dosimetry system.  
1.2 The PMMA dosimeter is classified as a Type II dosimeter on the basis of the complex effect of influence quantities (see ISO/ASTM Practice 52628).  
1.3 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM 52628 “Practice for Dosimetry in Radiation Processing” for a PMMA dosimetry system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.  
1.4 This practice covers the use of PMMA dosimetry systems under the following conditions:  
1.4.1 the absorbed dose range is 0.1 kGy to 150 kGy.  
1.4.2 the absorbed dose rate is 1 × 10−2 to 1 × 107 Gy·s−1.  
1.4.3 the photon energy range is 0.1 to 25 MeV.  
1.4.4 the electron energy range is 3 to 25 MeV.  
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.6 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 The purpose of irradiation of dried spices, herbs, and vegetable seasonings is to control pathogenic bacteria, molds, and yeasts present in these commodities (2-7).  
4.2 The process will also kill any insects present, at all stages of development.
Note 2: CAC/RCP 19-1979 of the Codex Alimentarius identifies the essential practices to be implemented to achieve effective radiation processing of food, in general, in a manner that maintains quality and yields food commodities that are safe and suitable for consumption.
SCOPE
1.1 This guide covers procedures for irradiation of dried spices, herbs, and vegetable seasonings for microbiological control. Generally, these items have moisture content of 4.5 to 12 % and are available in whole, ground, chopped, or other finely divided forms, or as blends. The blends may contain sodium chloride and minor amounts of dry food materials ordinarily used in such blends.  
1.2 This guide covers gamma, electron beam, and X-radiation treatment. This guide also covers low energy electron beam treatment where only part of the product is irradiated (that is, surface treatment).  
1.3 This guide covers absorbed doses ranging from 3 to 30 kilogray (kGy).
Note 1: U.S. regulations permit a maximum dose of 30 kGy. (See 21CFR 179.26.) EU regulations permit a maximum dose of 10 kGy. (See Directive 1999/3/EC.)  
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.5 This document is one of a set of standards that provides recommendations for properly implementing and utilizing radiation processing. It is intended to be read in conjunction with Practice ISO/ASTM 52628.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
3.1 The purpose of this standard is to facilitate communication and promote common understanding within the professionals in radiation processing research and industry.  
3.2 Unambiguous communication of concepts is crucial taking into account the relevant implications that may arise from misunderstandings with regard to equipment and materials involved in the standards dealing with any subject regarding radiation processing activities. Concepts dealing with dosimetry related to radiation processing and procedures for preparation, testing, and using dosimetry systems to determine the absorbed dose are present in all standards developed by E61 and ISO/TC85/WG3 and need to be designated by common terms and described by harmonized definitions in order to avoid misunderstandings.
SCOPE
1.1 This terminology standard lists terms and definitions related to radiation processing concepts, especially radiation dose measurements. Use of this standard, and the common terminology, will foster clearer communication, and remove ambiguity.  
1.2 The use of ionizing radiation for the treatment of commercial products such as the sterilization of medical devices, the reduction of microbial contamination in food or the modification of polymers is referred to as radiation processing. The types of radiation used may be gamma radiation (typically from cobalt-60 sources), X-radiation or accelerated electrons.  
1.3 This standard provides terms and definitions for dosimetry for radiation processing concepts dealing with procedures related to operational qualification, performance qualification, and routine processing that may influence absorbed dose in the products, and types of dosimetry systems that may be used during calibration or on a routine basis as part of quality assurance in commercial radiation processing of products.  
1.4 When selecting terms and definitions, special care has been taken to include the terms that need to be defined, that is to say, either because the definitions are essential to the correct understanding of the corresponding concepts or because some specific ambiguities need to be addressed.  
1.5 The “Discussion” appended to certain definitions offers clarification or examples to facilitate understanding of the concepts described. In certain cases, miscellaneous information is also included, for example, the units in which a quantity is normally measured, recommended parameter values, references, etc.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 The ECB dosimetry system provides a reliable means of measuring absorbed dose to water. It is based on a process of radiolytic formation of hydrochloric acid (HCl) in aqueous ethanolic solutions of chlorobenzene by ionizing radiation ((7, 8) , ICRU 80).  
4.2 The dosimeters are partly deoxygenated solutions of chlorobenzene (CB) in 96 volume % ethanol in an appropriate container, such as a flame-sealed glass ampoule. Radiation chemical yields (G) for the formation of HCl in typical ECB solution formulations are given in Table 1. (A) The ratio of the photon mass energy-absorption coefficients for water and the dosimeter solution at  60Co gamma ray energy:
(B) Radiation chemical yield of HCl in the dose range from 100 Gy to 100 kGy.(C) Upper dose range 20 kGy.(D) Lower dose range 1 kGy. This formulation also contained 0.04 % acetone and 0.04 % benzene.  
4.3 The irradiated solutions indicate absorbed dose by the amount of HCl formed. A number of analytical methods are available for measuring the amount of HCl in ethanol (10) .  
4.4 The concentration of chlorobenzene in the solution can be varied so as to simulate a number of materials in terms of the photon mass energy-absorption coefficients (μen/ρ) for X- and gamma radiation, and electron mass collision stopping powers (S/ρ), over a broad energy range from 10−2 to 100 MeV  (11-14).  
4.5 The ECB dosimetry system may be used with other radiation types, such as neutrons (15) , and protons (16). Meaningful dosimetry of any radiation types and energies novel to the system's use requires that the respective radiation chemical responses applicable under the circumstances be established in advance.
SCOPE
1.1 This practice covers the preparation, handling, testing, and procedure for using the ethanol-chlorobenzene (ECB) dosimetry system to measure absorbed dose to water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the system will be referred to as the ECB system. The ECB dosimeter is classified as a type I dosimeter on the basis of the effect of influence quantities. The ECB dosimetry system may be used as a reference standard dosimetry system or as a routine dosimetry system.  
1.2 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for the ECB system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.  
1.3 This practice describes the mercurimetric titration analysis as a standard readout procedure for the ECB dosimeter when used as a reference standard dosimetry system. Other readout methods (spectrophotometric, oscillometric) that are applicable when the ECB system is used as a routine dosimetry system are described in Annex A1 and Annex A2.  
1.4 This practice applies only to gamma radiation, X-radiation/bremsstrahlung, and high energy electrons.  
1.5 This practice applies provided the following conditions are satisfied:  
1.5.1 The absorbed dose range is between 10 Gy and 2 MGy for gamma radiation and between 10 Gy and 200 kGy for high current electron accelerators (1, 2).2 (Warning—the boiling point of ethanol chlorobenzene solutions is approximately 80 °C. Ampoules may explode if the temperature during irradiation exceeds the boiling point. This boiling point may be exceeded if an absorbed dose greater than 200 kGy is given in a short period of time.)  
1.5.2 The absorbed-dose rate is less than 106 Gy s−1(2).  
1.5.3 For radionuclide gamma-ray sources, the initial photon energy is greater than 0.6 MeV. For bremsstrahlung photons, the energy of the electrons used to produce the bremsstrahlung photons is equal to or greater than 2 MeV. For electron beams, the initial electron energy is greater than 8 MeV (3).
Note 1: The same response r...

SIGNIFICANCE AND USE
4.1 The ceric-cerous system provides a reliable means for determining absorbed dose to water. It is based on a process of reduction of ceric ions to cerous ions in acidic aqueous solution by ionizing radiation (1, 4, ICRU Report 80).
Note 3: The ceric-cerous system described in the practice has cerous sulfate added to the initial solution to reduce the effect of organic impurities and to allow the potentiometric method of measurement. Other systems used for dosimetry include solutions of ceric sulfate or ceric ammonium sulfate in sulfuric acid without the initial addition of cerous sulfate. These other systems are based on the same process of reduction of ceric ions to cerous ions but are not included in this practice.
SCOPE
1.1 This practice covers the preparation, testing, and procedure for using the ceric-cerous sulfate dosimetry system to measure absorbed dose to water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the system will be referred to as the ceric-cerous system. The ceric-cerous dosimeter is classified as a type 1 dosimeter on the basis of the effect of influence quantities. The ceric-cerous system may be used as a reference standard dosimetry system or as a routine dosimetry system.  
1.2 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for the ceric-cerous system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.  
1.3 This practice describes both the spectrophotometric and the potentiometric readout procedures for the ceric-cerous system.  
1.4 This practice applies only to gamma radiation, X-radiation/bremsstrahlung, and high energy electrons.  
1.5 This practice applies provided the following conditions are satisfied:  
1.5.1 The absorbed-dose range is from 5 × 102 to 5 × 104 Gy (1).2  
1.5.2 The absorbed-dose rate does not exceed 106 Gy s−1 (1).  
1.5.3 For radionuclide gamma-ray sources, the initial photon energy is greater than 0.6 MeV. For bremsstrahlung photons, the initial energy of the electrons used to produce the bremsstrahlung photons is equal to or greater than 2 MeV. For electron beams, the initial electron energy is greater than 8 MeV.
Note 1: The lower energy limits are appropriate for a cylindrical dosimeter ampoule of 12-mm diameter. Corrections for dose gradient across the ampoule may be required for electron beams (2). The ceric-cerous system may be used at lower energies by employing thinner (in the beam direction) dosimeters (see ICRU Report 35).  
1.5.4 The irradiation temperature of the dosimeter is above 0°C and below 62°C (3).
Note 2: The temperature coefficient of dosimeter response is known only in this range (see 5.2). Use outside this range requires determination of the temperature coefficient.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

SIGNIFICANCE AND USE
4.1 Blood and blood components are irradiated to predetermined absorbed doses to inactivate viable lymphocytes to help prevent transfusion-induced graft-versus-host disease (GVHD) in certain immunocompromised patients and those receiving related-donor products (1, 2).9  
4.2 The assurance that blood and blood components have been properly irradiated is of crucial importance for patient health. This shall be demonstrated by means of accurate absorbed-dose measurements on the product, or in simulated product.  
4.3 Blood and blood components are usually irradiated using gamma radiation from 137Cs or 60Co sources, or X-radiation from X-ray units.  
4.4 Blood irradiation specifications include a lower limit of absorbed dose, and may include an upper limit or central target dose. For a given application, any of these values may be prescribed by regulations that have been established on the basis of available scientific data (see 2.6).  
4.5 For each blood irradiator, an absorbed-dose rate at a reference position within the canister is measured as part of irradiator acceptance testing using a reference-standard dosimetry system. That reference-standard measurement is used to establish operating parameters so as to deliver specified dose to blood and blood components.  
4.6 Absorbed-dose measurements are performed within the blood or blood-equivalent volume for determining the absorbed-dose distribution. Such measurements are often performed using simulated product (for example, polystyrene is considered blood equivalent for 137Cs photon energies).  
4.7 Dosimetry is part of a measurement management system that is applied to ensure that the radiation process meets predetermined specifications (see ISO/ASTM Practice 52628).  
4.8 Blood and blood components are usually irradiated in chilled or frozen condition. Care should be taken, therefore, to ensure that the dosimeters and radiation-sensitive indicators can be used under such temperature conditions.  
4.9 Proper ...
SCOPE
1.1 This practice outlines the irradiator installation qualification program and the dosimetric procedures to be followed during operational qualification and performance qualification of the irradiator. Procedures for the routine radiation processing of blood product (blood and blood components) are also given. If followed, these procedures will help ensure that blood product exposed to gamma radiation or X-radiation (bremsstrahlung) will receive absorbed doses with a specified range.  
1.2 This practice covers dosimetry for the irradiation of blood product for self-contained irradiators (free-standing irradiators) utilizing radionuclides such as 137Cs and  60Co, or X-radiation (bremsstrahlung). The absorbed dose range for blood irradiation is typically 15 Gy to 50 Gy.  
1.3 The photon energy range of X-radiation used for blood irradiation is typically from 40 keV to 300 keV.  
1.4 This practice also covers the use of radiation-sensitive indicators for the visual and qualitative indication that the product has been irradiated (see ISO/ASTM Guide 51539).  
1.5 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for dosimetry performed for blood irradiation. It is intended to be read in conjunction with ISO/ASTM Practice 52628.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides ...

SIGNIFICANCE AND USE
4.1 Use as an Analytical Tool—Mathematical methods provide an analytical tool to be employed for many applications related to absorbed dose determinations in radiation processing. Mathematical calculations may not be used as a substitute for routine dosimetry in some applications (for example, medical device sterilization, food irradiation).  
4.2 Dose Calculation—Absorbed-dose calculations may be performed for a variety of photon/electron environments and irradiator geometries.  
4.3 Evaluate Process Effectiveness—Mathematical models may be used to evaluate the impact of changes in product composition, loading configuration, and irradiator design on dose distribution.  
4.4 Complement or Supplement to Dosimetry—Dose calculations may be used to establish a detailed understanding of dose distribution, providing a spatial resolution not obtainable through measurement. Calculations may be used to reduce the number of dosimeters required to characterize a procedure or process (for example, dose mapping).  
4.5 Alternative to Dosimetry—Dose calculations may be used when dosimetry is impractical (for example, granular materials, materials with complex geometries, material contained in a package where dosimetry is not practical or possible).  
4.6 Facility Design—Dose calculations are often used in the design of a new irradiator and can be used to help optimize dose distribution in an existing facility or radiation process. The use of modeling in irradiator design can be found in Refs (2-7).  
4.7 Validation—The validation of the model should be done through comparison with reliable and traceable dosimetric measurements. The purpose of validation is to demonstrate that the mathematical method makes reliable predictions of dose and other transport quantities. Validation compares predictions or theory to the results of an appropriate experiment. The degree of validation is commensurate with the application. Guidance is given in the documents referenced in Annex A2.  
...
SCOPE
1.1 This guide describes different mathematical methods that may be used to calculate absorbed dose and criteria for their selection. Absorbed-dose calculations can determine the effectiveness of the radiation process, estimate the absorbed-dose distribution in product, or supplement or complement, or both, the measurement of absorbed dose.  
1.2 Radiation processing is an evolving field and annotated examples are provided in Annex A6 to illustrate the applications where mathematical methods have been successfully applied. While not limited by the applications cited in these examples, applications specific to neutron transport, radiation therapy and shielding design are not addressed in this document.  
1.3 This guide covers the calculation of radiation transport of electrons and photons with energies up to 25 MeV.  
1.4 The mathematical methods described include Monte Carlo, point kernel, discrete ordinate, semi-empirical and empirical methods.  
1.5 This guide is limited to the use of general purpose software packages for the calculation of the transport of charged or uncharged particles and photons, or both, from various types of sources of ionizing radiation. This standard is limited to the use of these software packages or other mathematical methods for the determination of spatial dose distributions for photons emitted following the decay of 137Cs or 60Co, for energetic electrons from particle accelerators, or for X-rays generated by electron accelerators.  
1.6 This guide assists the user in determining if mathematical methods are a useful tool. This guide may assist the user in selecting an appropriate method for calculating absorbed dose. The user must determine whether any of these mathematical methods are appropriate for the solution to their specific application and what, if any, software to apply.
Note 1: The user is urged to apply these predictive techniques while being aware of the need for experien...

SIGNIFICANCE AND USE
4.1 Radiation processing of articles in both commercial and research applications may be carried out for a number of purposes. These include, for example, sterilization of health care products, reduction of the microbial populations in foods and modification of polymers. The radiations used may be accelerated electrons, gamma-radiation from radionuclide sources such as cobalt-60, or X-radiation.  
4.2 To demonstrate control of radiation processes that are dependent on the delivery of a known dose, the absorbed dose must be measured using a dosimetry system, the calibration of which, is traceable to appropriate national or international standards. The radiation-induced change in the dosimeter is evaluated and related to absorbed dose through calibration. Dose measurements required for particular processes are described in other standards referenced in this practice.
SCOPE
1.1 This practice describes the basic requirements that apply when making absorbed dose measurements in accordance with the ASTM E61 series of dosimetry standards. In addition, it provides guidance on the selection of dosimetry systems and directs the user to other standards that provide specific information on individual dosimetry systems, calibration methods, uncertainty estimation and radiation processing applications.  
1.2 This practice applies to dosimetry for radiation processing applications using electrons or photons (gamma- or X-radiation).  
1.3 This practice addresses the minimum requirements of a measurement management system, but does not include general quality system requirements.  
1.4 This practice does not address personnel dosimetry or medical dosimetry.  
1.5 This practice does not apply to primary standard dosimetry systems.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 This guide is intended to provide direction on dosimetry for experiments in food and agricultural research, and on the reporting of dosimetry results. Research concerning the effectiveness of irradiation of food and agricultural products to achieve a defined benefit involves very different absorbed-dose specifications from one study and one product to another. For example, the absorbed dose required to sterilize fruit flies is much lower than the doses required to inactivate some bacterial pathogens in meat, or to decontaminate spices.
Note 4: Examples of the relevant effects of irradiation include reduction of viable food-borne bacteria, viruses and parasites and phytosanitary treatment (such as disinfestation of fruits and vegetables), prevention of sprouting, delay of ripening, and changes in product chemistry and quality. Further discussion of these effects is outside the scope of this guide. Refer to ASTM Guides F1355, F1356, F1736 and F1885.  
4.2 Proper reporting of the irradiation aspect is important since the degree of biological effect may be a function of various factors such as the radiation source, the absorbed-dose rate, energy of the incident radiation, environmental effects during irradiation, and the type of incident radiation. This guide attempts to highlight the information, including the methodology and results of the absorbed-dose measurements, necessary for an experiment to be repeatable by other researchers.
Note 5: Factors that may influence the response of agricultural products to ionizing radiation include genus, species, variety, vigor, life stage, initial quality, state of ripeness, temperature, moisture content, pH, packaging, shipping, and storage conditions. Although these factors are not discussed in this guide, they should be considered when planning experiments (see ASTM Guides F1355, F1356, F1640, F1736 and F1885.  
4.3 Ideally, an experiment should be designed to irradiate the sample as uniformly as possible. In practice...
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1.1 This guide covers the minimum requirements for dosimetry needed to conduct research on the effect of radiation on food and agricultural products. Such research includes establishment of the quantitative relationship between absorbed dose and the relevant effects in these products. This guide also describes the overall need for dosimetry in such research, and in reporting of the results. Dosimetry must be considered as an integral part of the experiment.
Note 1: The Codex Alimentarius Commission has developed an international General Standard and a Code of Practice that address the application of ionizing radiation to the treatment of foods and that strongly emphasize the role of dosimetry for ensuring that irradiation will be properly performed  (1).2
Note 2: This guide includes tutorial information in the form of Notes. Researchers should also refer to the references provided at the end of the standard, and other applicable scientific literature, to assist in the experimental methodology as applied to dosimetry (2-10).  
1.2 This guide covers research conducted using the following types of ionizing radiation: gamma radiation, X-ray (bremsstrahlung), and electron beams.  
1.3 This guide describes dosimetry requirements for establishing the experimental method and for routine experiments. It does not include dosimetry requirements for installation qualification or operational qualification of the irradiation facility. These subjects are treated in ISO/ASTM Practices 51204, 51431, 51608, 51649, and 51702.  
1.4 This guide is not intended to limit the flexibility of the experimenter in the determination of the experimental methodology. The purpose of the guide is to ensure that the radiation source and experimental methodology are chosen such that the results of the experiment will be useful and understandable to other scientists and regulatory agencies.  
1.5 The overall uncertainty in the absorbed-dose measure...

SIGNIFICANCE AND USE
4.1 Use as an Analytical Tool—Mathematical methods provide an analytical tool to be employed for many applications related to absorbed dose determinations in radiation processing. Mathematical calculations may not be used as a substitute for routine dosimetry in some applications (for example, medical device sterilization, food irradiation).  
4.2 Dose Calculation—Absorbed-dose calculations may be performed for a variety of photon/electron environments and irradiator geometries.  
4.3 Evaluate Process Effectiveness—Mathematical models may be used to evaluate the impact of changes in product composition, loading configuration, and irradiator design on dose distribution.  
4.4 Complement or Supplement to Dosimetry—Dose calculations may be used to establish a detailed understanding of dose distribution, providing a spatial resolution not obtainable through measurement. Calculations may be used to reduce the number of dosimeters required to characterize a procedure or process (for example, dose mapping).  
4.5 Alternative to Dosimetry—Dose calculations may be used when dosimetry is impractical (for example, granular materials, materials with complex geometries, material contained in a package where dosimetry is not practical or possible).  
4.6 Facility Design—Dose calculations are often used in the design of a new irradiator and can be used to help optimize dose distribution in an existing facility or radiation process. The use of modeling in irradiator design can be found in Refs (2-7).  
4.7 Validation—The validation of the model should be done through comparison with reliable and traceable dosimetric measurements. The purpose of validation is to demonstrate that the mathematical method makes reliable predictions of dose and other transport quantities. Validation compares predictions or theory to the results of an appropriate experiment. The degree of validation is commensurate with the application. Guidance is given in the documents referenced in Annex A2.  
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1.1 This guide describes different mathematical methods that may be used to calculate absorbed dose and criteria for their selection. Absorbed-dose calculations can determine the effectiveness of the radiation process, estimate the absorbed-dose distribution in product, or supplement or complement, or both, the measurement of absorbed dose.  
1.2 Radiation processing is an evolving field and annotated examples are provided in Annex A6 to illustrate the applications where mathematical methods have been successfully applied. While not limited by the applications cited in these examples, applications specific to neutron transport, radiation therapy and shielding design are not addressed in this document.  
1.3 This guide covers the calculation of radiation transport of electrons and photons with energies up to 25 MeV.  
1.4 The mathematical methods described include Monte Carlo, point kernel, discrete ordinate, semi-empirical and empirical methods.  
1.5 This guide is limited to the use of general purpose software packages for the calculation of the transport of charged or uncharged particles and photons, or both, from various types of sources of ionizing radiation. This standard is limited to the use of these software packages or other mathematical methods for the determination of spatial dose distributions for photons emitted following the decay of 137Cs or 60Co, for energetic electrons from particle accelerators, or for X-rays generated by electron accelerators.  
1.6 This guide assists the user in determining if mathematical methods are a useful tool. This guide may assist the user in selecting an appropriate method for calculating absorbed dose. The user must determine whether any of these mathematical methods are appropriate for the solution to their specific application and what, if any, software to apply.
Note 1: The user is urged to apply these predictive techniques while being aware of the need for experien...

SIGNIFICANCE AND USE
4.1 The judicious selection of a contact material is part of Good Manufacturing Practices (GMPs) for the irradiation of prepackaged foods. This guide recognizes the need to evaluate the impact of packaging materials on the safety and quality of foods irradiated to control the proliferation of food-borne pathogens, as well as their impact on foods irradiated for other purposes, such as prevention of re-infestation, delay of ripening, or shelf-life extension.  
4.2 As part of the evaluation, the selection process should consider the effects of irradiation on the chemical and physical properties of the contact material.  
4.3 Packaging is not considered to be a food preservation technique for overcoming any deficiencies attributable to inadequate GMPs during preparation, storage, or treatment of foods to be irradiated. The quality of the irradiated food will depend heavily on its initial quality, control of the irradiation process, storage temperature and handling of the food after irradiation.
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1.1 This guide provides a format to assist producers and users of food in selecting contact materials that have the desirable characteristics for their intended use and that comply with applicable standards or government authorizations. It outlines parameters that should be considered when selecting food contact materials intended for use during irradiation of prepackaged foods and it examines the criteria for fitness for their use.  
1.2 This guide identifies known regulations and regulatory frameworks worldwide pertaining to contact materials for holding foods during irradiation, but it does not address all regulatory issues associated with the selection and use of packaging materials for foods to be irradiated. It is the responsibility of the user of this guide to determine the pertinent regulatory issues in each country where foods are to be irradiated and where irradiated foods are distributed.  
1.3 This guide does not address all of the food safety issues associated with the synergistic effects of irradiation and packaging as food preservation techniques on the extension of shelf life or food quality. It is the responsibility of the user of this guide to determine the critical food safety issues and to conduct appropriate product assessment tests to determine the compatibility between the packaging application and irradiation relative to changes in sensory attributes and shelf life.  
1.4 This guide does not address the use of irradiation as a processing aid for the production or sterilization of food packaging materials.  
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 Absorbed doses of or below 1 kGy can inactivate some parasites, such as the broad fish tapeworm (Dibothrocephalus latus) (2).  
4.2 Absorbed doses below 10 kGy can reduce or eliminate vegetative cells of pathogenic sporeforming and non-sporeforming microorganisms, such as Clostridia spp., Vibrio spp., Salmonellae, Listeria monocytogenes, or Staphylococcus aureus, that may be present in fresh or frozen product.  
4.2.1 Absorbed doses below 10 kGy can reduce the numbers of some spores, but are not adequate to reduce the potential health risk from microbial spores or toxins (3).  
4.3 Absorbed doses below 10 kGy can reduce or eliminate the vegetative cells of sporeforming and non-sporeforming microorganisms, such as Bacillus or Pseudomonas species, that cause spoilage of fresh product, thus extending refrigerated shelf life in many cases (4).
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1.1 This guide outlines procedures and operations for the irradiation of raw, untreated, fresh (chilled), or frozen finfish and aquatic invertebrates, while ensuring that the irradiated product is safe and wholesome.  
1.1.1 Aquatic invertebrates include molluscs, crustacea, echinoderms, etc.
1.1.1.1 Molluscs include bivalve shellfish, such as clams, mussels, and oysters; snails; and cephalopods, such as squid and octopus.
1.1.1.2 Crustacea include shellfish such as shrimp, lobster, crabs, prawns and crayfish.
1.1.1.3 Echinoderms include sea urchins and sea cucumbers.  
1.2 This guide covers absorbed doses used to reduce the microbial and parasite populations in aquatic invertebrates and finfish. Such doses typically are below 10 kGy (1).2  
1.3 The use of reduced-oxygen packaging (vacuum or modified atmosphere, and including products packed in oil) with irradiated, raw product is not covered by this guide. The anaerobic environment created by reduced-oxygen packaging provides the potential for outgrowth of, and toxin production from, Clostridium botulinum spores.  
1.4 This guide does not cover the irradiation of smoked or dried fish to reduce microbial load or to control insect infestation.  
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory requirements prior to use.

SIGNIFICANCE AND USE
4.1 The principal purpose of irradiation is to help ensure the safety of these foods for human consumption. Irradiation significantly reduces the numbers of pathogenic bacteria such as Campylobacter, Shiga toxin-Producing E coli, Listeria monocytogenes, Salmonella, Staphylococcus aureus, or Yersinia enterocolitica.
Note 3: Ionizing radiation doses below 10 kGy will reduce but may not eliminate spores of pathogenic bacteria uncluding those of Clostridium botulinum, Clostridium perfringens, and Bacillus cereus.  
4.2 The process also inactivates parasites such as Trichinella spiralis and Toxoplasma gondii.  
4.3 The process may extend the shelf life of fresh meat and poultry by reducing the numbers of viable, spoilage bacteria, such as Pseudomonas species and lactic acid bacilli.  
4.4 Radiation processing of fresh, frozen, or processed meat and poultry is a critical control point (CCP) of a Hazard Analysis of Critical Control Points (HACCP) program. It serves as an important measure to control any residual risk from pathogenic microorganisms before the product reaches the consumer (4).  
4.5 The “Recommended International Code of Practice for Radiation-Processing of Food” (CAC/RCP 19-1979) of the Codex Alimentarius identifies the essential practices to be implemented to achieve effective radiation processing of food, in general, in a manner that maintains quality and yields food products that are safe and suitable for consumption.
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1.1 This guide outlines procedures for the irradiation of fresh, frozen, or processed meat and poultry.
Note 1: The Codex Alimentarius Commission defines meat as “the edible part of any mammal” and poultry as “any domesticated bird, including chicken, turkeys, ducks, geese, guinea-fowls, or pigeons” (CAC/MISC 5).
Note 2: Current U.S. regulations limit the definition of meat and poultry as listed in 9 CFR Section 301.2 and 381.1, respectively. (2, 3).  
1.2 This guide covers the use of ionizing radiation to eliminate or reduce the numbers of vegetative, pathogenic microorganisms and parasites, and to extend the refrigerated shelf-life of those products by reducing the numbers of spoilage microorganisms in fresh, frozen, or processed meat and poultry. The absorbed dose for this application is typically less than 10 kGy.  
1.3 This guide addresses irradiation of pre-packaged product for retail sale or for use as an ingredient in other products. It also addresses the in-line irradiation of unpackaged product. Other specific ISO and ASTM standards exist for the irradiation of food. In those areas covered by ISO 14470, that standard takes precedence.  
1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 Blood and blood components are irradiated to predetermined absorbed doses to inactivate viable lymphocytes to help prevent transfusion-induced graft-versus-host disease (GVHD) in certain immunocompromised patients and those receiving related-donor products (1, 2).9  
4.2 The assurance that blood and blood components have been properly irradiated is of crucial importance for patient health. This shall be demonstrated by means of accurate absorbed-dose measurements on the product, or in simulated product.  
4.3 Blood and blood components are usually irradiated using gamma radiation from 137Cs or 60Co sources, or X-radiation from X-ray units.  
4.4 Blood irradiation specifications include a lower limit of absorbed dose, and may include an upper limit or central target dose. For a given application, any of these values may be prescribed by regulations that have been established on the basis of available scientific data (see 2.6).  
4.5 For each blood irradiator, an absorbed-dose rate at a reference position within the canister is measured as part of irradiator acceptance testing using a reference-standard dosimetry system. That reference-standard measurement is used to establish operating parameters so as to deliver specified dose to blood and blood components.  
4.6 Absorbed-dose measurements are performed within the blood or blood-equivalent volume for determining the absorbed-dose distribution. Such measurements are often performed using simulated product (for example, polystyrene is considered blood equivalent for 137Cs photon energies).  
4.7 Dosimetry is part of a measurement management system that is applied to ensure that the radiation process meets predetermined specifications (see ISO/ASTM Practice 52628).  
4.8 Blood and blood components are usually irradiated in chilled or frozen condition. Care should be taken, therefore, to ensure that the dosimeters and radiation-sensitive indicators can be used under such temperature conditions.  
4.9 Proper ...
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1.1 This practice outlines the irradiator installation qualification program and the dosimetric procedures to be followed during operational qualification and performance qualification of the irradiator. Procedures for the routine radiation processing of blood product (blood and blood components) are also given. If followed, these procedures will help ensure that blood product exposed to gamma radiation or X-radiation (bremsstrahlung) will receive absorbed doses with a specified range.  
1.2 This practice covers dosimetry for the irradiation of blood product for self-contained irradiators (free-standing irradiators) utilizing radionuclides such as 137Cs and  60Co, or X-radiation (bremsstrahlung). The absorbed dose range for blood irradiation is typically 15 Gy to 50 Gy.  
1.3 The photon energy range of X-radiation used for blood irradiation is typically from 40 keV to 300 keV.  
1.4 This practice also covers the use of radiation-sensitive indicators for the visual and qualitative indication that the product has been irradiated (see ISO/ASTM Guide 51539).  
1.5 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for dosimetry performed for blood irradiation. It is intended to be read in conjunction with ISO/ASTM Practice 52628.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and to determine the applicability or regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 This guide is one of a set of guides and practices that provide recommendations for properly implementing dosimetry in radiation processing. In order to understand and effectively use this and other dosimetry standards, consider first “Practice for Dosimetry in Radiation Processing,” ASTM/ISO 52628, which describes the basic requirements that apply when making absorbed dose measurements in accordance with the ASTM E10.01 series of dosimetry standards. In addition, ASTM/ISO 52628 provides guidance on the selection of dosimetry systems and directs the user to other standards that provide information on individual dosimetry systems, calibration methods, uncertainty estimation and radiation processing applications.  
4.2 Radiation processing is carried out under fixed path conditions where (a) a process load is automatically moved through the radiation field by mechanical means or (b) a process load is irradiated statically by manually placing product at predetermined positions before the process is started. In both cases the process is controlled in such a manner that the process load position(s) and orientation(s) are reproducible within specified limits.
Note 2: Static irradiation encompasses irradiation of the process load using either manual rotation, no rotation or automated rotation.  
4.3 Some radiation processing facilities that utilize a fixed conveyor path for routine processing may also characterize a region within the radiation field for static radiation processing, sometimes referred to as “Off Carrier” processing.  
4.4 Many radiation processing applications require a minimum absorbed dose (to achieve a desired effect or to fulfill a legal requirement), and a maximum absorbed dose (to ensure that the product, material or substance still meets functional specifications or to fulfill a legal requirement).  
4.5 Information from the dose mapping is used to:  
4.5.1 Characterize the radiation process and assess the reproducibility of absorbed-dose...
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1.1 This document provides guidance in determining absorbed-dose distributions (mapping) in products, materials or substances irradiated in gamma, X-ray (bremsstrahlung) and electron beam facilities.
Note 1: For irradiation of food and the radiation sterilization of health care products, specific ISO and ISO/ASTM standards containing dose mapping requirements exist. See ISO/ASTM Practices 51431, 51608, 51649, 51702 and 51818 and ISO 11137-1. Regarding the radiation sterilization of health care products, in those areas covered by ISO 11137-1, that standard takes precedence.  
1.2 This guide is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing. it is intended to be read in conjunction with ISO/ASTM 52628.  
1.3 Methods of analyzing the dose map data are described. Examples are provided of statistical methods that may be used to analyze dose map data.  
1.4 Dose mapping for bulk flow processing and fluid streams is not discussed.  
1.5 Dosimetry is an element of a total quality management system for an irradiation facility. Other controls besides dosimetry may be required for specific applications such as medical device sterilization and food preservation.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory requirements prior to use.

SIGNIFICANCE AND USE
4.1 The Fricke dosimetry system provides a reliable means for measurement of absorbed dose to water, based on a process of oxidation of ferrous ions to ferric ions in acidic aqueous solution by ionizing radiation (ICRU 80, PIRS-0815,(4)). In situations not requiring traceability to national standards, this system can be used for absolute determination of absorbed dose without calibration, as the radiation chemical yield of ferric ions is well characterized (see Appendix X3).  
4.2 The dosimeter is an air-saturated solution of ferrous sulfate or ferrous ammonium sulfate that indicates absorbed dose by an increase in optical absorbance at a specified wavelength. A temperature-controlled calibrated spectrophotometer is used to measure the absorbance.
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1.1 This practice covers the procedures for preparation, testing and using the acidic aqueous ferrous ammonium sulfate solution dosimetry system to measure absorbed dose to water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. The system will be referred to as the Fricke dosimetry system. The Fricke dosimetry system may be used as either a reference standard dosimetry system or a routine dosimetry system.  
1.2 This practice is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for the Fricke dosimetry system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.  
1.3 The practice describes the spectrophotometric analysis procedures for the Fricke dosimetry system.  
1.4 This practice applies only to gamma radiation, X-radiation (bremsstrahlung), and high-energy electrons.  
1.5 This practice applies provided the following are satisfied:  
1.5.1 The absorbed dose range shall be from 20 to 400 Gy (1).2  
1.5.2 The absorbed-dose rate does not exceed 106 Gy·s−1 (2).  
1.5.3 For radioisotope gamma sources, the initial photon energy is greater than 0.6 MeV. For X-radiation (bremsstrahlung), the initial energy of the electrons used to produce the photons is equal to or greater than 2 MeV. For electron beams, the initial electron energy is greater than 8 MeV.  
Note 1: The lower energy limits given are appropriate for a cylindrical dosimeter ampoule of 12 mm diameter. Corrections for displacement effects and dose gradient across the ampoule may be required for electron beams  (3). The Fricke dosimetry system may be used at lower energies by employing thinner (in the beam direction) dosimeter containers (see ICRU Report 35).  
1.5.4 The irradiation temperature of the dosimeter should be within the range of 10 to 60°C.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 A variety of products and materials are irradiated with X-radiation to modify their characteristics and improve the economic value or to reduce their microbial population for health-related purposes. Dosimetry requirements might vary depending on the type and end use of the product. Some examples of irradiation applications where dosimetry may be used are:  
4.1.1 Sterilization of health care products;  
4.1.2 Treatment of food for the purpose of parasite and pathogen control, insect disinfestation, and shelf life extension;  
4.1.3 Disinfection of consumer products;  
4.1.4 Cross-linking or degradation of polymers and elastomers;  
4.1.5 Curing composite material;  
4.1.6 Polymerization of monomers and oligomer and grafting of monomers onto polymers;  
4.1.7 Enhancement of color in gemstones and other materials;  
4.1.8 Modification of characteristics of semiconductor devices; and  
4.1.9 Research on materials effects of irradiation.
Note 3: Dosimetry with measurement traceability and with known measurement uncertainty is required for regulated irradiation processes, such as the sterilization of health care products and treatment of food. Dosimetry may be less important for other industrial processes, such as polymer modification, which can be evaluated by changes in the physical properties of the irradiated materials. Nevertheless, routine dosimetry may be used to monitor the reproducibility of the radiation process.  
4.2 Radiation processing specifications usually include a pair of absorbed-dose limits: a minimum value to ensure the intended beneficial effect and a maximum value that the product can tolerate while still meeting its functional or regulatory specifications. For a given application, one or both of these values may be prescribed by process specifications or regulations. Knowledge of the dose distribution within irradiated material is essential to help meet these requirements. Dosimetry is essential to the radiation process since it i...
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1.1 This practice outlines the dosimetric procedures to be followed during installation qualification, operational qualification, performance qualification and routine processing at an X-ray (bremsstrahlung) irradiator. Other procedures related to operational qualification, performance qualification and routine processing that may influence absorbed dose in the product are also discussed.
Note 1: Dosimetry is only one component of a total quality assurance program for adherence to good manufacturing practices used in radiation processing applications.
Note 2: ISO/ASTM Practices 51649, 51818 and 51702 describe dosimetric procedures for electron beam and gamma facilities for radiation processing.  
1.2 For radiation sterilization of health care products, see ISO 11137-1, Sterilization of health care products – Radiation – Part 1: Requirements for development, validation and routine control of a sterilization process for medical devices. In those areas covered by ISO 11137-1, that standard takes precedence.  
1.3 For irradiation of food, see ISO 14470, Food irradiation – Requirements for development, validation and routine control of the process of irradiation using ionizing radiation for the treatment of food. In those areas covered by ISO 14470, that standard takes precedence.  
1.4 This document is one of a set of standards that provides recommendations for properly implementing and utilizing dosimetry in radiation processing. It is intended to be read in conjunction with ISO/ASTM Practice 52628, “Practice for Dosimetry in Radiation Processing”.  
1.5 In contrast to monoenergetic gamma radiation, the X-ray energy spectrum extends from low values (about 35 keV) up to the maximum energy of the electrons incident on the X-ray target (see Section 5 and Annex A1).  
1.6 Information about effective or regulatory dose limits and energy limits for X-ray applications is not within the scope of this practice.  
1.7 This ...

SIGNIFICANCE AND USE
4.1 All measurements, including dose measurements, have an associated uncertainty. The magnitude of the measurement uncertainty is important for assessing the quality of the results of the measurement system.  
4.2 Information on the range of achievable uncertainty values for specific dosimetry systems is given in the ISO/ASTM standards for the specific dosimetry systems. While the uncertainty values given in specific dosimetry standards are achievable, it should be noted that both smaller and larger uncertainty values might be obtained depending on measurement conditions and instrumentation. For more information see also ISO/ASTM 52628.  
4.3 This guide uses the methodology adopted by the GUM for estimating uncertainties in measurements (see 2.4). Therefore, components of uncertainty are evaluated as either Type A uncertainty or Type B uncertainty.  
4.4 Quantifying individual components of uncertainty may assist the user in identifying actions to reduce the measurement uncertainty.  
4.5 Periodically, the uncertainty should be reassessed to confirm the existing estimate. Should changes occur that could influence the existing component estimates or result in the addition of new components of uncertainty, a new estimate of uncertainty should be established.  
4.6 Although this guide provides a framework for assessing uncertainty, it cannot substitute for critical thinking, intellectual honesty, and professional skill. The evaluation of uncertainty is neither a routine task nor a purely mathematical one; it depends on detailed knowledge of the nature of the measurand and of the measurement method and procedure used. The quality and utility of the uncertainty quoted for the result of a measurement therefore ultimately depends on the understanding, critical analysis, and integrity of those who contribute to the assignment of its value (JCGM 100:2008).
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1.1 This standard provides guidance on the use of concepts described in the JCGM Evaluation of Measurement Data – Guide to the Expression of Uncertainty in Measurement (GUM) to estimate the uncertainties in the measurement of absorbed dose in radiation processing.  
1.2 Methods are given for identifying, evaluating and estimating the components of measurement uncertainty associated with the use of dosimetry systems and for calculating combined standard measurement uncertainty and expanded (overall) uncertainty of dose measurements based on the GUM methodology.  
1.3 Examples are given on how to develop a measurement uncertainty budget and a statement of uncertainty.  
1.4 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and provides guidance for achieving compliance with the requirements of ISO/ASTM 52628 related to the evaluation and documentation of the uncertainties associated with measurements made with a dosimetry system. It is intended to be read in conjunction with ISO/ASTM 52628, ISO/ASTM 51261 and ISO/ASTM 52701.  
1.5 This guide does not address the establishment of process specifications or conformity assessment.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 Various products and materials are routinely irradiated at pre-determined doses at electron beam facilities to preserve or modify their characteristics. Dosimetry requirements may vary depending on the radiation process and end use of the product. A partial list of processes where dosimetry may be used is given below.  
4.1.1 Polymerization of monomers and grafting of monomers onto polymers,  
4.1.2 Cross-linking or degradation of polymers,  
4.1.3 Curing of composite materials,  
4.1.4 Sterilization of health care products,  
4.1.5 Disinfection of consumer products,  
4.1.6 Food irradiation (parasite and pathogen control, insect disinfestation, and shelf-life extension),  
4.1.7 Control of pathogens and toxins in drinking water,  
4.1.8 Control of pathogens and toxins in liquid or solid waste,  
4.1.9 Modification of characteristics of semiconductor devices,  
4.1.10 Color enhancement of gemstones and other materials, and  
4.1.11 Research on radiation effects on materials.  
4.2 Dosimetry is used as a means of monitoring the irradiation process.
Note 2: Dosimetry with measurement traceability and known uncertainty is required for regulated radiation processes such as sterilization of health care products (see ISO 11137-1 and Refs (1-36)) and preservation of food (see ISO 14470 and Ref (4)). It may be less important for other processes, such as polymer modification, which may be evaluated by changes in the physical and chemical properties of the irradiated materials. Nevertheless, routine dosimetry may be used to monitor the reproducibility of the treatment process.
Note 3: Measured dose is often characterized as absorbed dose in water. Materials commonly found in single-use disposable medical devices and food are approximately equivalent to water in the absorption of ionizing radiation. Absorbed dose in materials other than water may be determined by applying conversion factors (5, 6).  
4.3 An irradiation process usually requires a minimum ab...
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1.1 This practice outlines dosimetric procedures to be followed in installation qualification (IQ), operational qualification (OQ) and performance qualifications (PQ), and routine processing at electron beam facilities.  
1.2 The electron beam energy range covered in this practice is between 300 keV and 25 MeV, although there are some discussions for other energies.  
1.3 Dosimetry is only one component of a total quality assurance program for adherence to good manufacturing practices used in radiation processing applications. Other measures besides dosimetry may be required for specific applications such as health care product sterilization and food preservation.  
1.4 Specific standards exist for the radiation sterilization of health care products and the irradiation of food. For the radiation sterilization of health care products, see ISO 11137-1 (Requirements) and ISO 11137-3 (Guidance on dosimetric aspects). For irradiation of food, see ISO 14470. In those areas covered by these standards, they take precedence. Information about effective or regulatory dose limits for food products is not within the scope of this practice (see ASTM Guides F1355, F1356, F1736, and F1885).  
1.5 This document is one of a set of standards that provides recommendations for properly implementing and utilizing dosimetry in radiation processing. It is intended to be read in conjunction with ISO/ASTM 52628, “Practice for Dosimetry in Radiation Processing”.
Note 1: For guidance in the calibration of routine dosimetry systems, see ISO/ASTM Practice 51261. For further guidance in the use of specific dosimetry systems, see relevant ISO/ASTM Practices. For discussion of radiation dosimetry for pulsed radiation, see ICRU Report 34.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health pract...

SIGNIFICANCE AND USE
4.1 The purpose of radiation treatment, as discussed in this guide, is to minimize the pest risk and to maximize the safety associated with the movement and use of fresh agricultural produce.  
4.2 Irradiation as a phytosanitary treatment can prevent development or emergence of the adult stage where adults are not present in the agricultural produce (for example, fruit flies) or sterilize the adult where that stage is present (for example, weevils). (4)
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1.1 This guide provides procedures for the radiation processing of fresh agricultural produce, for example, fruits, vegetables, and cut flowers, as a phytosanitary treatment. This guide is directed primarily toward the treatment needed to control regulated pests commonly associated with fresh agricultural produce.  
1.2 The typical absorbed dose range used for phytosanitary treatments is between 150 gray (Gy) and 600 gray (Gy). The practical minimum or maximum dose of a treatment may be higher or lower than this range, depending on the type of pest to be controlled and the radiation tolerance of a particular type of fruit. If the minimum effective dose necessary to achieve the desired phytosanitary effect is greater than the radiation tolerance of the produce, then irradiation is not an appropriate treatment (see 5.2).  
1.3 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 The dichromate system provides a reliable means for measuring absorbed dose to water. It is based on a process of reduction of dichromate ions to chromic ions in acidic aqueous solution by ionizing radiation.  
4.2 The dosimeter is a solution containing silver and dichromate ions in perchloric acid in an appropriate container such as a sealed glass ampoule. The solution indicates absorbed dose by a change (decrease) in optical absorbance at a specified wavelength(s) ((3), ICRU Report 80). A calibrated spectrophotometer is used to measure the absorbance.
SCOPE
1.1 This practice covers the preparation, testing, and procedure for using the acidic aqueous silver dichromate dosimetry system to measure absorbed dose to water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the system will be referred to as the dichromate system. The dichromate dosimeter is classified as a type I dosimeter on the basis of the effect of influence quantities. The dichromate system may be used as either a reference standard dosimetry system or a routine dosimetry system.  
1.2 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for the dichromate dosimetry system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.  
1.3 This practice describes the spectrophotometric analysis procedures for the dichromate system.  
1.4 This practice applies only to gamma radiation, X-radiation/bremsstrahlung, and high energy electrons.  
1.5 This practice applies provided the following conditions are satisfied:  
1.5.1 The absorbed dose range is from 2 × 10 3 to 5 × 104 Gy.  
1.5.2 The absorbed dose rate does not exceed 600 Gy/pulse (12.5 pulses per second), or does not exceed an equivalent dose rate of 7.5 kGy/s from continuous sources (1).2  
1.5.3 For radionuclide gamma sources, the initial photon energy shall be greater than 0.6 MeV. For bremsstrahlung photons, the initial energy of the electrons used to produce the bremsstrahlung photons shall be equal to or greater than 2 MeV. For electron beams, the initial electron energy shall be greater than 8 MeV. Note 1—The lower energy limits given are appropriate for a cylindrical dosimeter ampoule of 12 mm diameter. Corrections for displacement effects and dose gradient across the ampoule may be required for electron beams (2). The dichromate system may be used at lower energies by employing thinner (in the beam direction) dosimeter containers (see ICRU Report 35).  
1.5.4 The irradiation temperature of the dosimeter shall be above 0°C and should be below 80°C. Note 2—The temperature coefficient of dosimeter response is known only in the range of 5 to 50°C (see 5.2). Use outside this range requires determination of the temperature coefficient.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. Specific precautionary statements are given in 9.3.

SIGNIFICANCE AND USE
4.1 Ionizing radiation produces physical or chemical changes in many materials that can be measured and related to absorbed dose. Materials with radiation-induced changes that have been thoroughly studied can be used as dosimeters in radiation processing. Note 3—The scientific basis for commonly used dosimetry systems and detailed descriptions of the radiation-induced interactions are given in ICRU Report 80.  
4.2 Before a material can be considered for use as a dosimeter, certain characteristics related to manufacture and measurement of its response to ionizing radiation need to be considered, including:  
4.2.1 the ability to manufacture batches of the material with evidence demonstrating a reproducible radiation-induced change,  
4.2.2 the availability of instrumentation for measuring this change, and  
4.2.3 the ability to take into account effects of influence quantities on the dosimeter response and on the measured absorbed-dose values.  
4.3 Dosimeter/dosimetry system characterization is conducted to determine the performance characteristics for a dosimeter/dosimetry system related to its capability for measuring absorbed dose. The information obtained from dosimeter/dosimetry system characterization includes the reproducibility of the measured absorbed-dose value, the useful absorbed-dose range, effects of influence quantities, and the conditions under which the dosimeters can be calibrated and used effectively.Note 4—When dosimetry systems are calibrated under the conditions of use, effects of influence quantities may be minimized or eliminated, because the effects can be accounted for or incorporated into the calibration method (see ISO/ASTM Practice 51261).  
4.4 The influence quantities of importance might differ for different radiation processing applications and facilities. For references to standards describing different applications and facilities, see ISO/ASTM Practice 52628.  
4.5 Classification of a dosimeter as a type I dosimeter or a t...
SCOPE
1.1 This guide provides guidance on determining the performance characteristics of dosimeters and dosimetry systems used in radiation processing.  
1.2 This guide describes the influence quantities that might affect the performance of dosimeters and dosimetry systems and that should be considered during dosimeter/dosimetry system characterization.  
1.3 Users of this guide are directed to existing standards and literature for procedures to determine the effects from individual influence quantities and from combinations of more than one influence quantity.  
1.4 Guidance is provided regarding the roles of the manufacturers, suppliers, and users in the characterization of dosimeters and dosimetry systems.  
1.5 This guide does not address how the dosimeter/dosimetry system characterization information is to be used in radiation processing applications or in the calibration of dosimetry systems.Note 1—For guidance on the use of dosimeter/dosimetry system characterization information for the selection and use of a dosimetry system, the user is directed to ISO/ASTM Practice 52628.Note 2—For guidance on the use of dosimeter/dosimetry system characterization information for dosimetry system calibration, the user is directed to ISO/ASTM Practice 51261.  
1.6 This guide does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 Radiation processing of articles in both commercial and research applications may be carried out for a number of purposes. These include, for example, sterilization of health care products, reduction of the microbial populations in foods and modification of polymers. The radiations used may be accelerated electrons, gamma-radiation from radionuclide sources such as cobalt-60, or X-radiation.  
4.2 To demonstrate control of the radiation process, the absorbed dose must be measured using a dosimetry system, the calibration of which, is traceable to appropriate national or international standards. The radiation-induced change in the dosimeter is evaluated and related to absorbed dose through calibration. Dose measurements required for particular processes are described in other standards referenced in this practice.
SCOPE
1.1 This practice describes the basic requirements that apply when making absorbed dose measurements in accordance with the ASTM E61 series of dosimetry standards. In addition, it provides guidance on the selection of dosimetry systems and directs the user to other standards that provide specific information on individual dosimetry systems, calibration methods, uncertainty estimation and radiation processing applications.  
1.2 This practice applies to dosimetry for radiation processing applications using electrons or photons (gamma- or X-radiation).  
1.3 This practice addresses the minimum requirements of a measurement management system, but does not include general quality system requirements.  
1.4 This practice does not address personnel dosimetry or medical dosimetry.  
1.5 This practice does not apply to primary standard dosimetry systems.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

SIGNIFICANCE AND USE
4.1 The assurance that blood and blood components have been properly irradiated is of crucial importance for patient health. The irradiator operator must demonstrate by means of accurate absorbed-dose measurements on the product, or in simulated product, that the specified absorbed dose has been achieved throughout the product.
4.2 Blood and blood components are irradiated at predetermined doses to inactivate viable lymphocytes to help prevent transfusion-induced graft-versus-host disease (GVHD) in certain immunocompromised patients and those receiving related-donor products (1, 2).6
4.3 Blood and blood components may be treated with ionizing radiation, such as gamma radiation from 137Cs or 60Co sources, and from self-contained X-ray (bremsstrahlung) units and medical linear X-ray (bremsstrahlung) and electron accelerators used primarily for radiotherapy.
4.3.1 The terms “gamma rays” and “gamma radiation” are used interchangeably, as are the terms “X-ray” and “Xradiation.”
4.4 Blood irradiation specifications include a lower limit of absorbed dose, and may include an upper limit or central target dose. For a given application, any of these values may be prescribed by regulations that have been established on the basis of available scientific data. See 2.4.
4.5 For each blood irradiator, an absorbed-dose rate at a reference position within the canister is measured by the manufacturer as part of acceptance testing using a reference-standard dosimetry system. That reference-standard measurement is used to calculate the timer setting required to deliver the specified absorbed dose to the center of the canister with blood and blood components, or other reference position. Either relative or absolute absorbed-dose measurements are performed within the blood- or blood-equivalent volume for determining the absorbed-dose distribution. Accurate radiation dosimetry at a reference position which could be the position of the maximum absorbed dose (Dmax) or minimum absorbed ...
SCOPE
1.1 This practice outlines irradiator installation qualification, operational qualification, performance qualification, and routine product processing dosimetric procedures to be followed in the irradiation of blood and blood components by the blood-banking community. If followed, these procedures will help to ensure that the products processed with ionizing radiation from gamma, X-radiation (bremsstrahlung), or electron sources receive absorbed doses within a predetermined range.
1.2 This practice covers dosimetry for the irradiation of blood for these types of irradiators: self-contained irradiators (free-standing irradiators) utilizing 137Cs, 60Co or X-radiation (bremsstrahlung), teletherapy units, and electron accelerators. The absorbed dose range for blood irradiation is typically 15 Gy to 50 Gy. In some jurisdictions, the absorbed dose range for blood irradiation is 25 Gy to 50 Gy.
1.3 The energy range is typically from approximately 40 keV to 5 MeV for photons, and up to 10 MeV for electrons.
1.4 This practice also covers the use of radiation-sensitive indicators for the visual and qualitative indication that the product has been irradiated.
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and to determine the applicability or regulatory limitations prior to use.