ASTM E2232-10

Standard Guide for Selection and Use of Mathematical Methods for Calculating Absorbed Dose in Radiation Processing Applications

SIGNIFICANCE AND USE
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).
Dose Calculation—Absorbed-dose calculations may be performed for a variety of photon/electron environments and irradiator geometries.
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.
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).
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).
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 references (3-9).
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.
Verification—Verification is ...
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 General purpose software packages are available for the calculation of the transport of charged and/or uncharged particles and photons 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 experience and also the inherent limitati...

General Information

• Status: Historical
• Publication Date: 30-Jun-2010
• ICS: 07.020 - Mathematics
• ICS: 17.240 - Radiation measurements
• Technical Committee: E61 - Radiation Processing
• Drafting Committee: E61.04 - Specialty Application

Relations

• Replaces: ASTM E2232-02 - Standard Guide for Selection and Use of Mathematical Methods for Calculating Absorbed Dose in Radiation Processing Applications
• Effective Date: 01-Jul-2010
• Referred By: ASTM ISO/ASTM51649-15 - Standard Practice for Dosimetry in an Electron Beam Facility for Radiation Processing at Energies Between 300 keV and 25 MeV
• Effective Date: 01-Jul-2010
• Referred By: ASTM E3270-21 - Standard Guide for Operational Qualification of Gamma Irradiators
• Effective Date: 01-Jul-2010
• Referred By: ASTM ISO/ASTM51608-15(2022) - Standard Practice for Dosimetry in an X-Ray (Bremsstrahlung) Facility for Radiation Processing at Energies between 50 keV and 7.5 MeV
• Effective Date: 01-Jul-2010
• Referred By: ASTM ISO/ASTM52303-15 - Standard Guide for Absorbed-Dose Mapping in Radiation Processing Facilities
• Effective Date: 01-Jul-2010
• Referred By: ASTM ISO/ASTM52628-20 - Standard Practice for Dosimetry in Radiation Processing
• Effective Date: 01-Jul-2010
• Referred By: ASTM ISO/ASTM51702-13(2021) - Standard Practice for Dosimetry in a Gamma Facility for Radiation Processing
• Effective Date: 01-Jul-2010
• Referred By: ASTM ISO/ASTM51818-20 - Standard Practice for Dosimetry in an Electron Beam Facility for Radiation Processing at Energies Between 80 and 300 keV
• Effective Date: 01-Jul-2010

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: E2232 − 10
Standard Guide for
Selection and Use of Mathematical Methods for Calculating
1
Absorbed Dose in Radiation Processing Applications
This standard is issued under the fixed designation E2232; 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.
beingawareoftheneedforexperienceandalsotheinherentlimitationsof
1. Scope
both the method and the available software. Information pertaining to
1.1 This guide describes different mathematical methods
availabilityandupdatestocodesformodelingradiationtransport,courses,
that may be used to calculate absorbed dose and criteria for workshops and meetings can be found in Annex A1. For a basic
understanding of radiation physics and a brief overview of method
their selection. Absorbed-dose calculations can determine the
selection, refer to Annex A3.
effectiveness of the radiation process, estimate the absorbed-
1.7 This standard does not purport to address all of the
dose distribution in product, or supplement or complement, or
safety concerns, if any, associated with its use. It is the
both, the measurement of absorbed dose.
responsibility of the user of this standard to establish appro-
1.2 Radiation processing is an evolving field and annotated
priate safety and health practices and determine the applica-
examples are provided in Annex A6 to illustrate the applica-
bility of regulatory requirements prior to use.
tions where mathematical methods have been successfully
applied. While not limited by the applications cited in these
2. Referenced Documents
examples, applications specific to neutron transport, radiation
2
2.1 ASTM Standards:
therapy and shielding design are not addressed in this docu-
E170Terminology Relating to Radiation Measurements and
ment.
Dosimetry
1.3 This guide covers the calculation of radiation transport
E482Guide for Application of Neutron Transport Methods
of electrons and photons with energies up to 25 MeV.
for Reactor Vessel Surveillance, E706 (IID)
2
1.4 The mathematical methods described include Monte 2.2 ISO/ASTM Standards:
Carlo, point kernel, discrete ordinate, semi-empirical and
51707Guide for Estimating Uncertainties in Dosimetry for
empirical methods. Radiation Processing
2.3 International Commission on Radiation Units and Mea-
1.5 General purpose software packages are available for the
3
surements Reports:
calculation of the transport of charged and/or uncharged
ICRU Report 60Fundamental Quantities and Units for
particlesandphotonsfromvarioustypesofsourcesofionizing
Ionizing Radiation
radiation. This standard is limited to the use of these software
ICRU Report 80Dosimetry Systems for Use in Radiation
packages or other mathematical methods for the determination
Processing
of spatial dose distributions for photons emitted following the
137 60
2.4 United States National Institute of Standards and Tech-
decay of Cs or Co, for energetic electrons from particle
4
nology:
accelerators, or for X-rays generated by electron accelerators.
NIST Technical Note 1297 (1994 edition)Guidelines for
1.6 This guide assists the user in determining if mathemati-
Evaluating and Expressing the Uncertainty of NIST Mea-
cal methods are a useful tool.This guide may assist the user in
surement Results
selecting an appropriate method for calculating absorbed dose.
The user must determine whether any of these mathematical
3. Terminology
methods are appropriate for the solution to their specific
3.1 Definitions:
application and what, if any, software to apply.
NOTE 1—The user is urged to apply these predictive techniques while
2
For referenced ASTM and ISO/ASTM standards, visit the ASTM website,
www.astm.org, or contact ASTM Customer Service at [e-mail]. For
1
This guide is under the jurisdiction of ASTM Committee E61 on Radiation Annual Book of ASTM Standards volume information, refer to the standard’s
Processing and is the direct responsibility of Subcommittee E61.04 on Specialty Document Summary page on the ASTM website.
3
Application. Available from International Commission on Radiation Units and
Current edition approved July 1, 2010. Published September 2010. Originally Measurements, 7910 Woodmont Ave., Suite 800, Bethesda, MD 20815 USA.
4
approved in 2002. Last previous edition approved in 2002 as E2232-02. DOI: Available as a download from the NIST web site at: http://physics.nist.gov/
10.1520/E2232-10. Pubs/guidelines/TN1297/tn1297s.pdf.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

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E2232 − 10
3.1.1 benchmark
...

This document is not anASTM standard and is intended only to provide the user of anASTM 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.
An American National Standard
Designation:E2232–02 Designation:E2232–10
Standard Guide for
Selection and Use of Mathematical Methods for Calculating
1
Absorbed Dose in Radiation Processing Applications
This standard is issued under the fixed designation E2232; 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. 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 and/or complement dosimetry measurements. or complement, or both, the measurement of
absorbed dose.
1.2 Radiation processing is an evolving field and annotated examples are provided inAnnexA4A6 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 in the energy range of 0.1with 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 General purpose software packages are available for the calculation of the transport of charged and/or neutraluncharged
particles and photons from various types of sources of ionizing radiation. This standard is limited to the use of these software
packagesorothermathematicalmethodsforthedeterminationofspatialdosedistributionsforphotonsemittedfollowingthedecay
137 60
of Cs or Co, energetic electrons from particle accelerators, or bremsstrahlung generated by electron accelerators.
1.6This 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. Co, 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 experience and also the inherent limitations of both
the method and the available software. Information pertaining to availability and updates to codes for modeling radiation transport, courses, workshops
and meetings can be found in Annex A1. For a basic understanding of radiation physics and a brief overview of method selection, refer to Annex A3.
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 and health practices and determine the applicability of regulatory
requirements prior to use.
2. Referenced Documents
2
2.1 ASTM Standards:
E170 Terminology Relating to Radiation Measurements and Dosimetry
2
E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID)
E666PracticeforCalculatingAbsorbedDoseFromGammaorXRadiationGuideforApplicationofNeutronTransportMethods
for Reactor Vessel Surveillance, E706 (IID)
2.2 ISO/ASTM Standards:
2
51204 Practice for Dosimetry in Gamma Irradiation Facilities for Food Processing
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.01 on
Radiation Processing: Dosimetry and Applications.
Current edition approved Sept. 10, 2002. Published November 2002. DOI: 10.1520/E2232-02.
Current edition approved July 1, 2010. Published September 2010. Originally approved in 2002. Last previous edition approved in 2002 as E2232-02. DOI:
10.1520/E2232-10.
2
For referenced ASTM and ISO/ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at [e-mail]. For Annual Book
of ASTM St
...