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ASTM E1026-13

(Practice)

Standard Practice for Using the Fricke Dosimetry System

Standard Practice for Using the Fricke Dosimetry System

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 (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 (ICRU 80).
SCOPE
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 Practice E2628 for the Fricke dosimetry system. It is intended to be read in conjunction with Practice E2628.  
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.

General Information

Status
Historical
Publication Date
31-Dec-2012
ICS
17.240 - Radiation measurements
Technical Committee
E61 - Radiation Processing
Drafting Committee
E61.02 - Dosimetry Systems
Current Stage
Ref Project

Relations

Replaces
ASTM E1026-04e1 - Standard Practice for Using the Fricke Reference-Standard Dosimetry System
Effective Date
01-Jan-2013
Replaced By
ASTM ISO/ASTM51026-15 - Standard Practice for Using the Fricke Dosimetry System
Effective Date
09-Feb-2015
Referred By
ASTM ISO/ASTM52701-13(2020) - Standard Guide for Performance Characterization of Dosimeters and Dosimetry Systems for Use in Radiation Processing
Effective Date
01-Jan-2013

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Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation: E1026 − 13 AnAmerican National Standard
Standard Practice for
1
Using the Fricke Dosimetry System
This standard is issued under the fixed designation E1026; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
beams (3).TheFrickedosimetrysystemmaybeusedatlowerenergiesby
1. Scope
employingthinner(inthebeamdirection)dosimetercontainers(seeICRU
1.1 This practice covers the procedures for preparation,
Report 35).
testingandusingtheacidicaqueousferrousammoniumsulfate
1.5.4 Theirradiationtemperatureofthedosimetershouldbe
solution dosimetry system to measure absorbed dose to water
within the range of 10 to 60°C.
when exposed to ionizing radiation. The system consists of a
dosimeter and appropriate analytical instrumentation. The
1.6 This standard does not purport to address all of the
system will be referred to as the Fricke dosimetry system. The
safety concerns, if any, associated with its use. It is the
Fricke dosimetry system may be used as either a reference
responsibility of the user of this standard to establish appro-
standard dosimetry system or a routine dosimetry system.
priate safety and health practices and determine the applica-
1.2 This practice is one of a set of standards that provides
bility of regulatory limitations prior to use.
recommendations for properly implementing dosimetry in
radiation processing, and describes a means of achieving
2. Referenced Documents
compliance with the requirements of Practice E2628 for the
3
2.1 ASTM Standards:
Fricke dosimetry system. It is intended to be read in conjunc-
C912Practice for Designing a Process for Cleaning Techni-
tion with Practice E2628.
cal Glasses
1.3 The practice describes the spectrophotometric analysis
E170Terminology Relating to Radiation Measurements and
procedures for the Fricke dosimetry system.
Dosimetry
1.4 This practice applies only to gamma radiation,
E178Practice for Dealing With Outlying Observations
X-radiation (bremsstrahlung), and high-energy electrons.
E275PracticeforDescribingandMeasuringPerformanceof
1.5 This practice applies provided the following are satis- Ultraviolet and Visible Spectrophotometers
fied: E666Practice for CalculatingAbsorbed Dose From Gamma
1.5.1 The absorbed dose range shall be from 20 to 400 Gy
or X Radiation
2
(1).
E668 Practice for Application of Thermoluminescence-
6 −1
1.5.2 The absorbed-dose rate does not exceed 10 Gy·s
Dosimetry (TLD) Systems for Determining Absorbed
(2).
DoseinRadiation-HardnessTestingofElectronicDevices
1.5.3 For radioisotope gamma sources, the initial photon
E925Practice for Monitoring the Calibration of Ultraviolet-
energy is greater than 0.6 MeV. For X-radiation
Visible Spectrophotometers whose Spectral Bandwidth
(bremsstrahlung), the initial energy of the electrons used to
does not Exceed 2 nm
produce the photons is equal to or greater than 2 MeV. For
E958Practice for Estimation of the Spectral Bandwidth of
electron beams, the initial electron energy is greater than 8
Ultraviolet-Visible Spectrophotometers
MeV.
E2628Practice for Dosimetry in Radiation Processing
NOTE1—Thelowerenergylimitsgivenareappropriateforacylindrical 3
2.2 ISO/ASTM Standards:
dosimeter ampoule of 12 mm diameter. Corrections for displacement
ISO/ASTM 51261Practice for Calibration of Routine Do-
effects and dose gradient across the ampoule may be required for electron
simetry Systems for Radiation Processing
ISO/ASTM 51707Guide for Estimating Uncertainties in
Dosimetry for Radiation Processing
1
This practice is under the jurisdiction of ASTM Committee E61 on Radiation
Processing and is the direct responsibility of Subcommittee E61.02 on Dosimetry
Systems.
Current edition approved Jan. 1, 2013. Published March 2013. Originally
ε1
3
approved in 1984. Last previous edition approved in 2004 as E1026–04 . DOI: For referenced ASTM and ISO/ASTM standards, visit the ASTM webiste,
10.1520/E1026-13. www.astm.org, or contact ASTM Customer Service at service@astm.org. For
2
The boldface numbers that appear in parentheses refer to a list of references at Annual Book of ASTM Standards volume information, refer to the standard’s
the end of this practice. Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E1026 − 13
2.3 ISO/IEC Standard: produced, destroyed, or changed by the mean energy, ε,
¯
ISO/IEC 17025General requirements for the competence of imparted to the matter.
4
testing and calibration laboratories
n x
~ !
G~x! 5 (2)
S D
2.4 Internat
...

This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
´1
Designation: E1026 − 04 E1026 − 13 An American National Standard
Standard Practice for
1
Using the Fricke Reference-Standard Dosimetry System
This standard is issued under the fixed designation E1026; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1
ε NOTE—Equations 3 and 4 were corrected editorially in August 2005.
1. Scope
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 system. It is classified as a reference-standard
dosimetry system (see ISO/ASTM 51261).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 Practice E2628 for the Fricke dosimetry
system. It is intended to be read in conjunction with Practice E2628.
1.3 The practice describes the spectrophotometric analysis procedures for the Fricke dosimeter.dosimetry system.
1.4 This practice applies only to gamma rays, x-raysradiation, X-radiation (bremsstrahlung), and high-energy electrons.
1.5 This practice applies provided the following are satisfied:
2
1.5.1 The absorbed dose range shall be from 20 to 400 Gy (1).
6 −1
1.5.2 The absorbed-dose rate does not exceed 10 Gy·s (2).
1.5.3 For radioisotope gamma-raygamma sources, the initial photon energy is greater than 0.6 MeV. For x-raysX-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 (see ICRU Reports 34 and 35). MeV.
NOTE 1—The lower energy limits given are appropriate for a cylindrical dosimeter ampoule of 12-mm outside12 mm diameter. Corrections for dose
gradients across an ampoule of that diameter or less are notdisplacement effects and dose gradient across the ampoule may be required for electron beams
required.(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.
2. Referenced Documents
3
2.1 ASTM Standards:
C912 Practice for Designing a Process for Cleaning Technical Glasses
D1193 Specification for Reagent Water
E170 Terminology Relating to Radiation Measurements and Dosimetry
E178 Practice for Dealing With Outlying Observations
E275 Practice for Describing and Measuring Performance of Ultraviolet and Visible Spectrophotometers
E666 Practice for Calculating Absorbed Dose From Gamma or X Radiation
1
This practice is under the jurisdiction of ASTM Committee E61 on Radiation Processing and is the direct responsibility of Subcommittee E61.02 on Dosimetry Systems.
Current edition approved Jan. 1, 2004Jan. 1, 2013. Published February 2004March 2013. Originally approved in 1984. Last previous edition approved in 20032004 as
ε1
E1026 – 03.E1026 – 04 . DOI: 10.1520/E1026-04E01.10.1520/E1026-13.
2
The boldface numbers that appear in parentheses refer to a list of references at the end of this practice.
3
For referenced ASTM and ISO/ASTM standards, visit the ASTM webiste, www.astm.org, or contact ASTM Customer Service at service@astm.org. For Annual Book
of ASTM Standards volume information, refer to the standard’s Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E1026 − 13
E668 Practice for Application of Thermoluminescence-Dosimetry (TLD) Systems for Determining Absorbe
...

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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  
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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.  
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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...

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ASTM
ASTM E3239-21(Guide)
Standard Guide for Using Statistical Process Control Principles for Routine Dosimetry in Radiation Processing

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.

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ASTM ISO/ASTM51310-22(Practice)
Standard Practice for Use of a Radiochromic Optical Waveguide Dosimetry System

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.

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ASTM
ASTM ISO/ASTM51261-13(2020)(Practice)
Standard Practice for Calibration of Routine Dosimetry Systems for Radiation Processing

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.

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ASTM ISO/ASTM52701-13(2020)(Guide)
Standard Guide for Performance Characterization of Dosimeters and Dosimetry Systems for Use in Radiation Processing

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 ...
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 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.

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ASTM ISO/ASTM52116-13(2020)(Practice)
Standard Practice for Dosimetry for a Self-Contained Dry-Storage Gamma Irradiator

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 ...

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