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...

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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: E2232 − 16
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,
workshops and meetings can be found in Annex A1. For a basic
their selection. Absorbed-dose calculations can determine the
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
1.7 This standard does not purport to address all of the
both, the measurement of absorbed dose.
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-
priate safety and health practices and determine the applica-
tions where mathematical methods have been successfully
bility of regulatory requirements prior to use.
applied. While not limited by the applications cited in these
examples, applications specific to neutron transport, radiation
2. Referenced Documents
therapy and shielding design are not addressed in this docu-
2
2.1 ASTM Standards:
ment.
E170Terminology Relating to Radiation Measurements and
1.3 This guide covers the calculation of radiation transport
Dosimetry
of electrons and photons with energies up to 25 MeV.
E482Guide for Application of Neutron Transport Methods
for Reactor Vessel Surveillance
1.4 The mathematical methods described include Monte
2
Carlo, point kernel, discrete ordinate, semi-empirical and
2.2 ISO/ASTM Standards:
empirical methods.
51707Guide for Estimating Uncertainties in Dosimetry for
Radiation Processing
1.5 This guide is limited to the use of general purpose
software packages for the calculation of the transport of
2.3 International Commission on Radiation Units and Mea-
3
charged or uncharged particles and photons, or both, from
surements Reports:
various types of sources of ionizing radiation. This standard is
ICRU Report 85aFundamental Quantities and Units for
limited to the use of these software packages or other math-
Ionizing Radiation
ematical methods for the determination of spatial dose distri-
2.4 United States National Institute of Standards and Tech-
137
4
butions for photons emitted following the decay of Cs or
nology:
60
Co, for energetic electrons from particle accelerators, or for
NIST Technical Note 1297 (1994 edition)Guidelines for
X-rays generated by electron accelerators.
Evaluating and Expressing the Uncertainty of NIST Mea-
1.6 This guide assists the user in determining if mathemati- surement Results
cal methods are a useful tool.This guide may assist the user in
3. Terminology
selecting an appropriate method for calculating absorbed dose.
The user must determine whether any of these mathematical
3.1 Definitions:
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,
www.astm.org, or contact ASTM Customer Service at service@astm.org. 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 Dec. 1, 2016. Published January 2017. Originally Measurements, 7910 Woodmont Ave., Suite 800, Bethesda, MD 20815 USA.
4
approved in 2002. Last previous edition approved in 2010 as E2232-10. DOI: Available as a download from the NIST web site at: http://physics.nist.gov/
10.1520/E2232-16. Pubs/guidelines/TN1297/tn1297s.pdf.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E2232 − 16
3.1.1 accuracy (VIM)—closeness of agreement between
...

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 − 10 E2232 − 16
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 General This guide is limited to the use of general purpose software packages are available for the calculation of the
transport of charged and/oror uncharged particles and photons 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
137 60
distributions for photons emitted following the decay of of Cs or 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 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
E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
2
2.2 ISO/ASTM Standards:
51707 Guide for Estimating Uncertainties in Dosimetry for Radiation Processing
3
2.3 International Commission on Radiation Units and Measurements Reports:
ICRU Report 6085a Fundamental Quantities and Units for Ionizing Radiation
ICRU Report 80 Dosimetry Systems for Use in Radiation Processing
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 July 1, 2010Dec. 1, 2016. Published September 2010January 2017. Originally approved in 2002. Last previous edition approved in 20022010
as E2232-02.E2232-10. DOI: 10.1520/E2232-10.10.1520/E2232-16.
2
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 Document Summary page on the ASTM website.
3
Available from International Commission on Radiation Units and Measurements, 7910 Woodmont Ave., Suite 800, Bethesda, MD 20815 USA.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United Sta
...

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