ASTM E666-14

Standard Practice for Calculating Absorbed Dose From Gamma or X Radiation

SIGNIFICANCE AND USE
4.1 The absorbed dose is a more meaningful parameter than exposure for use in relating the effects of radiation on materials. It expresses the energy absorbed by the irradiated material per unit mass, whereas exposure is related to the amount of charge produced in air per unit mass. Absorbed dose, as referred to here, implies that the measurement is made under conditions of charged particle (electron) equilibrium (see Appendix X1). In practice, such conditions are not rigorously achievable but, under some circumstances, can be approximated closely.  
4.2 Different materials, when exposed to the same radiation field, absorb different amounts of energy. Using the techniques of this standard, charged particle equilibrium must exist in order to relate the absorbed dose in one material to the absorbed dose in another. Also, if the radiation is attenuated by a significant thickness of an absorber, the energy spectrum of the radiation will be changed, and it will be necessary to correct for this.Note 1—For comprehensive discussions of various dosimetry methods applicable to the radiation types and energies and absorbed dose rate ranges discussed in this method, see ICRU Reports 34 and 80.
SCOPE
1.1 This practice presents a technique for calculating the absorbed dose in a material from knowledge of the radiation field, the composition of the material, (1-5)2,3 and a related measurement. The procedure is applicable for X and gamma radiation provided the energy of the photons fall within the range from 0.01 to 20 MeV.  
1.2 A method is given for calculating the absorbed dose in a material from the knowledge of the absorbed dose in another material exposed to the same radiation field. The procedure is restricted to homogeneous materials composed of the elements for which absorption coefficients have been tabulated. All 92 natural elements are tabulated in (2). It also requires some knowledge of the energy spectrum of the radiation field produced by the source under consideration. Generally, the accuracy of this method is limited by the accuracy to which the energy spectrum of the radiation field is known.  
1.3 The results of this practice are only valid if charged particle equilibrium exists in the material and at the depth of interest. Thus, this practice is not applicable for determining absorbed dose in the immediate vicinity of boundaries between materials of widely differing atomic numbers. For more information on this topic, see Practice E1249.  
1.4 Energy transport computer codes4 exist that are formulated to calculate absorbed dose in materials more precisely than this method. To use these codes, more effort, time, and expense are required. If the situation warrants, such calculations should be used rather than the method described here.  
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 and health practices and determine the applicability of regulatory limitations prior to use.

General Information

• Status: Historical
• Publication Date: 31-Dec-2013
• ICS: 17.240 - Radiation measurements
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.07 - Radiation Dosimetry for Radiation Effects on Materials and Devices

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: E666 − 14
Standard Practice for
1
Calculating Absorbed Dose From Gamma or X Radiation
This standard is issued under the fixed designation E666; 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.
This standard has been approved for use by agencies of the U.S. Department of Defense.
1. Scope than this method. To use these codes, more effort, time, and
expense are required. If the situation warrants, such calcula-
1.1 This practice presents a technique for calculating the
tions should be used rather than the method described here.
absorbed dose in a material from knowledge of the radiation
2,3
1.5 This standard does not purport to address all of the
field, the composition of the material, (1-5) and a related
safety concerns, if any, associated with its use. It is the
measurement. The procedure is applicable for X and gamma
responsibility of the user of this standard to establish appro-
radiation provided the energy of the photons fall within the
priate safety and health practices and determine the applica-
range from 0.01 to 20 MeV.
bility of regulatory limitations prior to use.
1.2 A method is given for calculating the absorbed dose in
a material from the knowledge of the absorbed dose in another
2. Referenced Documents
material exposed to the same radiation field. The procedure is
5
2.1 ASTM Standards:
restrictedtohomogeneousmaterialscomposedoftheelements
E170Terminology Relating to Radiation Measurements and
for which absorption coefficients have been tabulated. All 92
Dosimetry
natural elements are tabulated in (2). It also requires some
E668Practice for Application of Thermoluminescence-
knowledge of the energy spectrum of the radiation field
Dosimetry (TLD) Systems for Determining Absorbed
produced by the source under consideration. Generally, the
DoseinRadiation-HardnessTestingofElectronicDevices
accuracyofthismethodislimitedbytheaccuracytowhichthe
E1249Practice for Minimizing Dosimetry Errors in Radia-
energy spectrum of the radiation field is known.
tionHardnessTestingofSiliconElectronicDevicesUsing
1.3 The results of this practice are only valid if charged
Co-60 Sources
particle equilibrium exists in the material and at the depth of
2.2 International Commission on Radiation Units and Mea-
interest. Thus, this practice is not applicable for determining
6
surements (ICRU) Reports:
absorbeddoseintheimmediatevicinityofboundariesbetween
ICRUReport18SpecificationofHighActivityGamma-Ray
materials of widely differing atomic numbers. For more infor-
Sources
mation on this topic, see Practice E1249.
ICRUReport21RadiationDosimetry:ElectronswithInitial
4
1.4 Energy transport computer codes exist that are formu-
Energies Between 1 and 50 MeV
lated to calculate absorbed dose in materials more precisely
ICRUReport51RadiationQuantitiesandUnitsinRadiation
Protection Dosimetry
ICRU Report 60Radiation Fundamental Quantities and
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
Units for Ionizing Radiation
Technology and Applicationsand is the direct responsibility of Subcommittee
ICRU Report 34The Dosimetry of Pulsed Radiation
E10.07 on Radiation Dosimetry for Radiation Effects on Materials and Devices.
Current edition approved Jan. 1, 2014. Published February 2014. Originally
ICRU Report 80Dosimetry Systems for Use in Radiation
approved in 1978. Last previous edition approved in 2009 as E666-09. DOI:
Processing
10.1520/E0666-14.
2
The boldface numbers in parentheses refer to the list of references appended to
3. Terminology
this practice.
3
See also ICRU Report 80. For calculation of absorbed dose in dosimetry
3.1 energy fluence spectrum, ψ(E)—the product of the
systemsandmaterialsusedinradiationprocessing,massattenuationcoefficientsand
particle fluence spectrum (see Terminology E170) and the
mass-energy absorption coefficients for key elements, compounds and materials
used in radiation processing dosimetry over the photon range from 100 keV to 20
MeV are given in Appendix 1 of that report.
4 5
Information on and packages of computer codes can be obtained from The For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Radiation Safety Information Computational Center, Oak Ridge National contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6362. This information center Standards volume information, refer to the standard’s Document Summary page on
collects, organizes, evaluates, and disseminates shielding information related to the ASTM website.
6
radiation from reactors, weapons, and accelerators and
...

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: E666 − 09 E666 − 14
Standard Practice for
1
Calculating Absorbed Dose From Gamma or X Radiation
This standard is issued under the fixed designation E666; 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.
This standard has been approved for use by agencies of the U.S. Department of Defense.
1. Scope
1.1 This practice presents a technique for calculating the absorbed dose in a material from knowledge of the radiation field, the
2,3
composition of the material, (1-5) and a related measurement. The procedure is applicable for X and gamma radiation provided
the energy of the photons fall within the range from 0.01 to 20 MeV.
1.2 A method is given for calculating the absorbed dose in a material from the knowledge of the absorbed dose in another
material exposed to the same radiation field. The procedure is restricted to homogeneous materials composed of the elements for
which absorption coefficients have been tabulated tabulated. All 92 natural elements are tabulated in (2). It also requires some
knowledge of the energy spectrum of the radiation field produced by the source under consideration. Generally, the accuracy of
this method is limited by the accuracy to which the energy spectrum of the radiation field is known.
1.3 The results of this practice are only valid if charged particle equilibrium exists in the material and at the depth of interest.
Thus, this practice is not applicable for determining absorbed dose in the immediate vicinity of boundaries between materials of
widely differing atomic numbers. For more information on this topic, see Practice E1249.
4
1.4 Energy transport computer codes exist that are formulated to calculate absorbed dose in materials more precisely than this
method. To use these codes, more effort, time, and expense are required. If the situation warrants, such calculations should be used
rather than the method described here.
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 and health practices and determine the applicability of regulatory
limitations prior to use.
2. Referenced Documents
5
2.1 ASTM Standards:
E170 Terminology Relating to Radiation Measurements and Dosimetry
6
E380 Practice for Use of the International System of Units (SI) (the Modernized Metric System) (Withdrawn 1997)
E668 Practice for Application of Thermoluminescence-Dosimetry (TLD) Systems for Determining Absorbed Dose in
Radiation-Hardness Testing of Electronic Devices
E1249 Practice for Minimizing Dosimetry Errors in Radiation Hardness Testing of Silicon Electronic Devices Using Co-60
Sources
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applicationsand is the direct responsibility of Subcommittee E10.07 on
Radiation Dosimetry for Radiation Effects on Materials and Devices.
Current edition approved June 1, 2009Jan. 1, 2014. Published June 2009February 2014. Originally approved in 1997. Last previous edition approved in 20082009 as
E666-08.-09. DOI: 10.1520/E0666-09.10.1520/E0666-14.
2
The boldface numbers in parentheses refer to the list of references appended to this practice.
3
See also ICRU Report 80. For calculation of absorbed dose in biological materials such as tissue or bone, etc., ICRU Report 14 provides more information and procedures
for a more accurate calculation than this practice.dosimetry systems and materials used in radiation processing, mass attenuation coefficients and mass-energy absorption
coefficients for key elements, compounds and materials used in radiation processing dosimetry over the photon range from 100 keV to 20 MeV are given in Appendix 1 of
that report.
4
Information on and packages of computer codes can be obtained from The Radiation Safety Information Computational Center, Oak Ridge National Laboratory, P.O.
Box 2008, Oak Ridge, TN 37831-6362. This information center collects, organizes, evaluates, and disseminates shielding information related to radiation from reactors,
weapons, and accelerators and to radiation occurring in space.
5
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
volume
...