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ASTM ISO/ASTM51310-04(2012)

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Standard Practice for Use of a Radiochromic Optical Waveguide Dosimetry System

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 3.1.6. Examples of appropriate wavelengths for the analysis for specific dosimetry systems are provided by their manufacturers and in Refs (1) through (5).
4.2 In the application of a specific dosimetry system, absorbed dose is determined by use of a calibration curve traceable to national or international standards.
4.3 The absorbed dose determined is usually specified in water. Absorbed dose in other materials may be determined by applying the conversion factors discussed in ISO/ASTM Guide 51261.
NOTE 1—For a comprehensive discussion of various dosimetry methods applicable to the radiation types and energies discussed in this practice, see ICRU Reports 14, 17, and 34.
4.4 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).
SCOPE
This practice covers the procedures for handling, testing, and using a radiochromic optical waveguide dosimetry system to measure absorbed dose in materials irradiated by photons in terms of absorbed dose in water.
1.2 This practice applies to radiochromic optical waveguide dosimeters that can be used within part or all of the specified ranges as follows:
1.2.1 The absorbed dose range is from 1 to 10 000 Gy for photons.
1.2.2 The absorbed dose rate is from 0.001 to 1000 Gy/s.
1.2.3 The radiation energy range for photons is from 0.1 to 10 MeV.
1.2.4 The irradiation temperature range is from –78 to +60°C.
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.

General Information

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

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ASTM ISO/ASTM51310-04(2012) - Standard Practice for Use of a Radiochromic Optical Waveguide Dosimetry SystemASTM ISO/ASTM51310-04(2012) - Standard Practice for Use of a Radiochromic Optical Waveguide Dosimetry System
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ASTM ISO/ASTM51310-04(2012) - Standard Practice for Use of a Radiochromic Optical Waveguide Dosimetry System
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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
ISO/ASTM 51310:2004 (Reapproved 2012)(E)
Standard Practice for
Use of a Radiochromic Optical Waveguide Dosimetry
System
This standard is issued under the fixed designation ISO/ASTM 51310; the number immediately following the designation indicates the
year of original adoption or, in the case of revision, the year of last revision.
1. Scope E925 Practice for Monitoring the Calibration of Ultraviolet-
Visible Spectrophotometers whose Spectral Bandwidth
1.1 This practice covers the procedures for handling,
does not Exceed 2 nm
testing, and using a radiochromic optical waveguide dosimetry
E958 Practice for Estimation of the Spectral Bandwidth of
system to measure absorbed dose in materials irradiated by
Ultraviolet-Visible Spectrophotometers
photons in terms of absorbed dose in water.
E1026 Practice for Using the Fricke Dosimetry System
1.2 This practice applies to radiochromic optical waveguide
2.2 ISO/ASTM Standards:
dosimeters that can be used within part or all of the specified
51261 Guide for Selection and Calibration of Dosimetry
ranges as follows:
Systems for Radiation Processing
1.2.1 The absorbed dose range is from 1 to 10 000 Gy for
51400 Practice for Characterization and Performance of a
photons.
High-Dose Radiation Dosimetry Calibration Laboratory
1.2.2 The absorbed dose rate is from 0.001 to 1000 Gy/s.
51707 Guide for Estimating Uncertainties in Dosimetry for
1.2.3 The radiation energy range for photons is from 0.1 to
Radiation Processing
10 MeV.
2.3 International Commission on Radiation Units and Mea-
1.2.4 The irradiation temperature range is from –78 to
surements (ICRU) Reports:
+60°C.
ICRU Report 14 Radiation Dosimetry: X-Rays and Gamma
1.3 This standard does not purport to address all of the
RayswithMaximumPhotonEnergiesBetween0.6and50
safety concerns, if any, associated with its use. It is the
MeV
responsibility of the user of this standard to establish appro-
ICRUReport17 RadiationDosimetry:X–RaysGeneratedat
priate safety and health practices and determine the applica-
Potentials of 5 to 150 kV
bility of regulatory limitations prior to use.
ICRU Report 34 The Dosimetry of Pulsed Radiation
ICRU Report 60 Fundamental Quantities and Units for
2. Referenced documents
Ionizing Radiation
2.1 ASTM Standards:
3. Terminology
E170 Terminology Relating to Radiation Measurements and
Dosimetry
3.1 Definitions:
E275 PracticeforDescribingandMeasuringPerformanceof
3.1.1 analysis wavelength—wavelength used in a spectro-
Ultraviolet and Visible Spectrophotometers
photometric instrument for the measurement of optical absor-
E668 Practice for Application of Thermoluminescence-
bance or reflectance.
Dosimetry (TLD) Systems for Determining Absorbed
3.1.2 calibration curve—graphical representation of the do-
DoseinRadiation-HardnessTestingofElectronicDevices
simetry system’s response function.
3.1.3 dosimeter batch—quantity of dosimeters made from a
specific mass of material with uniform composition, fabricated
This guide is under the jurisdiction of ASTM Committee E61 on Radiation
in a single production run under controlled, consistent condi-
Processing and is the direct responsibility of Subcommittee E61.02 on Dosimetry
Systems, and is also under the jurisdiction of ISO/TC 85/WG 3. tions and having a unique identification code.
CurrenteditionapprovedMarch21,2012.PublishedNovember2012.Originally
3.1.4 dosimetry system—system used for determining ab-
ε1
published as ASTM E 1310–89. Last previous ASTM edition E 1310–98 . ASTM
sorbed dose, consisting of dosimeters, measurement instru-
E 1310–94 was adopted by ISO in 1998 with the intermediate designation ISO
15559:1998(E). The present International Standard ISO/ASTM
ments and their associated reference standards, and procedures
51310:2004(2012)(E) replaces ISO 15559 and is a reapproval of the last previous
for the system’s use.
edition ISO/ASTM 51310:2004(E).
For referenced ASTM and ISO/ASTM standards, visit the ASTM website,
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 Available from the International Commission on Radiation Units and
Document Summary page on the ASTM website. Measurements, 7910 Woodmont Ave., Suite 800, Bethesda, MD 20814, U.S.A.
© ISO/ASTM International 2022 – All rights reserved
ISO/ASTM 51310:2004 (2012)(E)
3.1.5 measurement quality assurance plan—documented 4.2 In the application of a specific dosimetry system,
program for the measurement process that ensures on a absorbed dose is determined by use of a calibration curve
continuing basis that the overall uncertainty meets the require- traceable to national or international standards.
mentsofthespecificapplication.Thisplanrequirestraceability
4.3 The absorbed dose determined is usually specified in
to, and consistency with, nationally or internationally recog-
water.Absorbed dose in other materials may be determined by
nized standards.
applyingtheconversionfactorsdiscussedinISO/ASTMGuide
3.1.6 net response, ∆R— radiation–induced change in the 51261.
relationship of measured absorbance at a specific wavelength
NOTE1—Foracomprehensivediscussionofvariousdosimetrymethods
determined by subtracting the pre–irradiation response, R ,
applicable to the radiation types and energies discussed in this practice,
from the post–irradiation response, R:
see ICRU Reports 14, 17, and 34.
∆R5 R 2 R (1)
4.4 These dosimetry systems commonly are applied in the
industrial radiation processing of a variety of products, for
with:
example, the sterilization of medical devices and radiation
A
λ processing of foods (4-6).
R 5
A
λref
Aλ
R (2) 5. Apparatus
0 5 0
F G
A
λref
5.1 The following shall be used to determine absorbed dose
and where:
with radiochromic optical waveguide dosimetry systems:
A = optical absorbance at the analysis wavelength,λ, and
λ
5.1.1 Dosimeters—A batch or portion of a batch of ra-
A = optical absorbance at a reference wavelength, λ .
λref ref
diochromic optical waveguide dosimeters.
3.1.7 optical waveguide—device that contains an optical
5.1.2 Spectrophotometer or Photometer—An instrument,
path at a high index of refraction relative to the material either a spectrophotometer equipped with a special dosimeter
enclosing the optical path.
holder and associated coupling optics (see Ref 7 for an
example), or a modified photometer (see Fig. 1 for a block
3.1.8 radiochromic optical waveguide—specially prepared
diagram of an instrument that uses a reference wavelength),
optical waveguide containing ingredients that undergo an
having documentation covering analysis wavelengths, accu-
ionizing radiation–induced change in photometric absorbance.
racy of wavelength selection, absorbance determination, spec-
This change in absorbance can be related to absorbed dose in
tral bandwidth, and stray light rejection.
water (1, 2).
5.1.3 Holder, to position the dosimeter reproducibly in the
3.1.9 reference wavelength, λ —wavelength selected for
ref
measuring light beam.
comparison with the analysis wavelength. This wavelength is
chosen to minimize effects associated with optical coupling
6. Performance check of instrumentation
and other geometric variations in the dosimeter.
6.1 Checkanddocumenttheperformanceofthephotometer
3.1.10 response function—mathematical representation of
or spectrophotometer (seeASTM Practices E275, E925, E958,
therelationshipbetweendosimeterresponseandabsorbeddose
and E1026). Use reference standards traceable to national or
for a given dosimetry system.
international standards, unless the photometer’s or spectropho-
3.2 Definitions or other terms used in this standard that tometer’s design precludes such use.
pertain to radiation measurement and dosimetry may be found 6.1.1 When using a photometer, check and document the
inASTM Terminology E170. Definitions in E170 are compat- accuracy of the absorbance scale at intervals not to exceed one
iblewithICRU60;thatdocument,therefore,maybeusedasan month during periods of use, or whenever there are indications
alternative reference.
of poor performance.
4. 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
waveguidecreatingand/ormodifyingopticalabsorbancebands
in the visible region of the spectrum. Optical response is
determined at selected wavelengths using the equations in
3.1.6.Examplesofappropriatewavelengthsfortheanalysisfor
specificdosimetrysystemsareprovidedbytheirmanufacturers
and in Refs (1-5).
The boldface numbers in parentheses refer to the bibliography at the end of this
practice. FIG. 1Block Diagram of the Instrument Described in Section 5
© ISO/ASTM International 2018 – All rights reserved
ISO/ASTM 51310:2004 (2012)(E)
6.1.2 Whenusingaspectrophotometer,checkanddocument 8.1.3 Visually inspect the dosimeters for imperfections (for
the precision and bias of the wavelength scale and absorbance example, loss of end fittings). Discard any dosimeters that
scale at or near the selected analysis wavelength(s) at intervals show imperfections.
not to exceed one month during periods of use, or whenever 8.1.4 Identify the dosimeters with an appropriate code that
there are indications of poor performance. can be related to the manufacturer, type, and batch.
6.1.3 Document the comparison of information obtained in 8.1.5 Store the dosimeters in accordance with the manufac-
turer’s written recommendations.
6.1.1 or 6.1.2 with the original instrument specification to
verify adequate performance.
8.2 Irradiation Procedure:
8.2.1 Determine the pre-irradiation response, R , for each
7. Calibration of the dosimetry system
dosimeter at the selected analysis wavelength(s). This may be
done for each dosimeter or by use of an average R determined
7.1 Prior to use, the dosimetry system (consisting of a
by reading several dosimeters and documenting the
specific batch of dosimeters and specific measurement instru-
uncertainty, provided this practice meets the precision require-
ments) shall be calibrated in accordance with the user’s
ments for the application.
documented procedure that specifies details of the calibration
8.2.2 Where necessary, package the dosimeters in a UV-
process and quality assurance requirements. This calibration
opaque material.
process shall be repeated at regular intervals to ensure that the
8.2.3 Mark the packaged dosimeters appropriately for iden-
accuracy of the absorbed dose measurement is maintained
tification.
within required limits. Calibration methods are described in
8.2.4 Irradiate the dosimeters.
ISO/ASTM Guide 51261.
NOTE 3—The dosimeters may be irradiated in the product undergoing
7.2 Calibration of Dosimeters—Irradiationisacriticalcom-
processingorinamediumofsimilarcomposition,orwater,ofappropriate
ponent of the calibration of the dosimetry system. Calibration
dimensions so as to approximate electron equilibrium conditions. Such
shall be performed in one of three ways by irradiating the
equilibrium conditions may not exist within dosimeters placed throughout
dosimeters at:
the product under actual processing conditions. This particularly is the
7.2.1 an accredited calibration laboratory that provides an case near interfaces of different materials. Irradiation under nonequilib-
rium conditions, such as on the surface of a product package, is often used
absorbed dose (or an absorbed-dose rate) having measurement
to monitor the absorbed dose delivered to the product and may be related
traceability to nationally or internationally recognized
totheabsorbeddosewithintheproductbycorrectionfactorsundercertain
standards, or
conditions.
7.2.2 an in-house calibration facility that provides an ab-
8.3 Analysis Procedure:
sorbed dose (or an absorbed-dose rate) having measurement
8.3.1 Avoid any exposure to stray ultraviolet radiation that
traceability to nationally or internationally recognized
may induce coloration of the dosimeter (see 8.1.1).
standards, or
8.3.2 Determine the post-irradiation response, R,atthe
7.2.3 a production or research irradiation facility together
selected analysis wavelength(s) used for calibration of the
with reference or transfer standard dosimeters that have mea-
dosimetry system.
surement traceability to nationally or internationally recog-
8.3.3 Calculate the net response, ∆ R, as follows:
nized standards.
∆R 5 R 2 R (3)
7.3 When the optical waveguide dosimeter is used as a
8.3.4 Determine the absorbed dose from the calibration
transfer standard dosimeter, the calibration irradiation may be
curve or response function.
performed only as stated in 7.2.1,orin 7.2.2 at a facility that
meets the requirements in ISO/ASTM Practice 51400.
9. Characterization of each batch of dosimeters
7.4 Measurement Instrument Calibration and Performance
9.1 Reproducibility of Net Response:
Verification—For the calibration of the instruments, and for the
9.1.1 Determine the reproducibility of net response for each
verification of instrument performance between calibrations,
batch of dosimeters by analyzing the data from the sets of
see ISO/ASTM Guide 51261 and/or instrument-specific oper-
dosimeters irradiated during the calibration process at each
ating manuals.
dose value.
9.1.2 Use the sample standard deviation (S ) determined
8. Procedure
n-1
during calibration to calculate the coefficient of variation (CV)
8.1 Examination and Storage Procedure:
for each dose value as follows:
8.1.1 Exposure to ultraviolet (UV) radiation may cause the
S
n21
dosimeter to change color. Perform tests to ensure that the
CV 5 100 3 (4)
F G
∆R
handling and reading environment does not cause measurable
color development. If needed, place UVfilters over fluorescent
9.1.3 Document these coefficients of variation and note any
lights or windows to reduce color development.
that are unusually large.
NOTE 2—Dosimeters may be stored in UV–opaque material to further
NOTE 4—In general, if the value of the coefficient of variation is greater
avoid the effects noted in 8.1.1.
than62 %, then a re-determination of the data should be considered or, in
the extreme, the batch should be rejected.
8.1.2 Handle the dosimeter along the sides, never at the
ends. Handling should be kept to a minimum. 9.2 Effect of Absorbed Dose Rate:
© ISO/ASTM International 2018 – All rights reserved
ISO/ASTM 51310:2004 (2012)(E)
9.2.1 The shape (slope) of the calibration curve associated 11. Minimum documentation
with some radiochromic optical waveguide dosimeters may be
11.1 Record the dosimeter manufacturer, type, batch
affected by the absorbed dose rate
...

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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).  
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SIGNIFICANCE AND USE
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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.  
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SIGNIFICANCE AND USE
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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...

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ASTM ISO/ASTM51649-22(Practice)
Standard Practice for Electron Beam Radiation Processing at Energies Between 300 keV and 25 MeV

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...
SCOPE
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...

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ASTM
ASTM ISO/ASTM51607-22(Practice)
Standard Practice for Use of an Alanine-EPR Dosimetry System

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).
SCOPE
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.

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ASTM
ASTM ISO/ASTM51702-13(2021)(Practice)
Standard Practice for Dosimetry in a Gamma Facility for Radiation Processing

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...
SCOPE
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...

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ASTM ISO/ASTM51650-21(Practice)
Standard Practice for Use of a Cellulose Triacetate Dosimetry System

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.

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ASTM ISO/ASTM51956-21(Practice)
Standard Practice for Use of a Thermoluminescence-Dosimetry System (TLD System) for Radiation Processing

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.
SCOPE
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.

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ASTM ISO/ASTM51401-21(Practice)
Standard Practice for Use of a Dichromate Dosimetry System

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.

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