ASTM E2232-21

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

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...

General Information

• Status: Published
• Publication Date: 14-Jun-2021
• ICS: 07.020 - Mathematics
• ICS: 17.240 - Radiation measurements
• Technical Committee: E61 - Radiation Processing
• Drafting Committee: E61.04 - Specialty Application

Standards Content (Sample)

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.
Designation: E2232 − 21
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.
NOTE 1—The user is urged to apply these predictive techniques while
1. Scope
beingawareoftheneedforexperienceandalsotheinherentlimitationsof
1.1 This guide describes different mathematical methods
both the method and the available software. Information pertaining to
that may be used to calculate absorbed dose and criteria for
availabilityandupdatestocodesformodelingradiationtransport,courses,
their selection. Absorbed-dose calculations can determine the
workshops and meetings can be found in Annex A1. For a basic
understanding of radiation physics and a brief overview of method
effectiveness of the radiation process, estimate the absorbed-
selection, refer to Annex A3.
dose distribution in product, or supplement or complement, or
both, the measurement of absorbed dose.
1.7 This standard does not purport to address all of the
safety concerns, if any, associated with its use. It is the
1.2 Radiation processing is an evolving field and annotated
responsibility of the user of this standard to establish appro-
examples are provided in Annex A6 to illustrate the applica-
tions where mathematical methods have been successfully priate safety, health, and environmental practices and deter-
applied. While not limited by the applications cited in these mine the applicability of regulatory limitations prior to use.
examples, applications specific to neutron transport, radiation
1.8 This international standard was developed in accor-
therapy and shielding design are not addressed in this docu-
dance with internationally recognized principles on standard-
ment.
ization established in the Decision on Principles for the
1.3 This guide covers the calculation of radiation transport Development of International Standards, Guides and Recom-
of electrons and photons with energies up to 25 MeV.
mendations issued by the World Trade Organization Technical
Barriers to Trade (TBT) Committee.
1.4 The mathematical methods described include Monte
Carlo, point kernel, discrete ordinate, semi-empirical and
2. Referenced Documents
empirical methods.
2
1.5 This guide is limited to the use of general purpose 2.1 ASTM Standards:
software packages for the calculation of the transport of
E482Guide for Application of Neutron Transport Methods
charged or uncharged particles and photons, or both, from
for Reactor Vessel Surveillance
various types of sources of ionizing radiation. This standard is
E3083Terminology Relating to Radiation Processing: Do-
limited to the use of these software packages or other math-
simetry and Applications
ematical methods for the determination of spatial dose distri-
2
2.2 ISO/ASTM Standards:
137
butions for photons emitted following the decay of Cs or
51707Guide for Estimating Uncertainties in Dosimetry for
60
Co, for energetic electrons from particle accelerators, or for
Radiation Processing
X-rays generated by electron accelerators.
52628Practice for Dosimetry in Radiation Processing
1.6 This guide assists the user in determining if mathemati-
3
2.3 ISO Standard:
cal methods are a useful tool.This guide may assist the user in
ISO 12749-4Nuclear energy, nuclear technologies, and
selecting an appropriate method for calculating absorbed dose.
radiological protection — Vocabulary — Part 4: Dosim-
The user must determine whether any of these mathematical
etry for radiation processing
methods are appropriate for the solution to their specific
application and what, if any, software to apply.
2
For referenced ASTM and ISO/ASTM standards, visit the ASTM website,
1
This guide is under the jurisdiction of ASTM Committee E61 on Radiation www.astm.org, or contact ASTM Customer Service at [e-mail]. For
Processing and is the direct responsibility of Subcommittee E61.04 on Specialty Annual Book of ASTM Standards volume information, refer to the standard’s
Application. Document Summary page on the ASTM website.
3
Current edition approved June 15, 2021. Published July 2021. Originally Available from International Organization for Standardization (ISO), ISO
approved in 2002. Last previous edition approved in 2020 as E2232-20. DOI: Central Secretariat, Chemin de Blandonnet 8, CP 401, 1214 Vernier, Geneva,
10.1520
...

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.
Designation: E2232 − 20 E2232 − 21
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 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
137 60
following the decay of Cs or 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, 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.
1
This guide is under the jurisdiction of ASTM Committee E61 on Radiation Processing and is the direct responsibility of Subcommittee E61.04 on Specialty Application.
Current edition approved Dec. 1, 2020June 15, 2021. Published March 2021July 2021. Originally approved in 2002. Last previous edition approved in 20162020 as
E2232-16.E2232-20. DOI: 10.1520/E2232-20.10.1520/E2232-21.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

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E2232 − 21
2. Referenced Documents
2
2.1 ASTM Standards:
E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
E3083 Terminology Relating to Radiation Processing: Dosimetry and Applications
2
2.2 ISO/ASTM Standards:
51707 Guide for Estimating Uncertainties in Dosimetry for Radiation Processing
52628 Practice for Dosimetry in Radiation Processing
3
2.3 ISO Standard:
ISO 12749-4 Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 4: Dosimetry for radiation
processing
4
2.4 International C
...