ASTM E666-03

Standard Practice for Calculating Absorbed Dose From Gamma or X Radiation

SIGNIFICANCE AND USE
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.
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 14, 21, and 34.
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) 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 (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 E 1249.
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.

General Information

• Status: Historical
• Publication Date: 09-Jul-2003
• 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

Relations

• Replaces: ASTM E666-97 - Standard Practice for Calculating Absorbed Dose From Gamma or X Radiation
• Effective Date: 10-Jul-2003
• Replaced By: ASTM E666-08 - Standard Practice for Calculating Absorbed Dose From Gamma or X Radiation
• Effective Date: 01-Nov-2008
• Referred By: ASTM ISO/ASTM51026-15 - Standard Practice for Using the Fricke Dosimetry System
• Effective Date: 10-Jul-2003
• Referred By: ASTM ISO/ASTM51956-13 - Standard Practice for Use of Thermoluminescence-Dosimetry (TLD) Systems for Radiation Processing
• Effective Date: 10-Jul-2003
• Referred By: ASTM E1161-21 - Standard Practice for Radiographic Examination of Semiconductors and Electronic Components
• Effective Date: 10-Jul-2003
• Referred By: ASTM F980-16 - Standard Guide for Measurement of Rapid Annealing of Neutron-Induced Displacement Damage in Silicon Semiconductor Devices
• Effective Date: 10-Jul-2003
• Referred By: ASTM ISO/ASTM51401-13 - Standard Practice for Use of a Dichromate Dosimetry System
• Effective Date: 10-Jul-2003
• Referred By: ASTM F773M-16 - Standard Practice for Measuring Dose Rate Response of Linear Integrated Circuits (Metric) (Withdrawn 2023)
• Effective Date: 10-Jul-2003
• Referred By: ASTM ISO/ASTM51538-17 - Standard Practice for Use of the Ethanol-Chlorobenzene Dosimetry System
• Effective Date: 10-Jul-2003
• Referred By: ASTM E668-20 - Standard Practice for Application of Thermoluminescence-Dosimetry (TLD) Systems for Determining Absorbed Dose in Radiation-Hardness Testing of Electronic Devices
• Effective Date: 10-Jul-2003
• Referred By: ASTM D1879-06(2023) - Standard Practice for Exposure of Adhesive Specimens to Ionizing Radiation
• Effective Date: 10-Jul-2003
• Referred By: ASTM F1892-12(2018) - Standard Guide for Ionizing Radiation (Total Dose) Effects Testing of Semiconductor Devices
• Effective Date: 10-Jul-2003
• Referred By: ASTM E1249-15(2021) - Standard Practice for Minimizing Dosimetry Errors in Radiation Hardness Testing of Silicon Electronic Devices Using Co-60 Sources
• Effective Date: 10-Jul-2003
• Referred By: ASTM F744M-16 - Standard Test Method for Measuring Dose Rate Threshold for Upset of Digital Integrated Circuits (Metric) (Withdrawn 2023)
• Effective Date: 10-Jul-2003
• Referred By: ASTM F996-11(2018) - Standard Test Method for Separating an Ionizing Radiation-Induced MOSFET Threshold Voltage Shift Into Components Due to Oxide Trapped Holes and Interface States Using the Subthreshold Current–Voltage Characteristics (Withdrawn 2023)
• Effective Date: 10-Jul-2003

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: E 666 – 03
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 (e) indicates an editorial change since the last revision or reapproval.
This standard has been approved for use by agencies of the Department of Defense.
1. Scope responsibility of the user of this standard to establish appro-
priate safety and health practices and determine the applica-
1.1 This practice presents a technique for calculating the
bility of regulatory limitations prior to use.
absorbed dose in a material from knowledge of the radiation
,
23
field, the composition of the material, (1-5) and a related
2. Referenced Documents
measurement. The procedure is applicable for X and gamma
2.1 ASTM Standards:
radiation provided the energy of the photons fall within the
E170 Terminology Relating to Radiation Measurements
range from 0.01 to 20 MeV.
5
and Dosimetry
1.2 A method is given for calculating the absorbed dose in
E380 Practice for Use of the International System of Units
a material from the knowledge of the absorbed dose in another
6
(SI) (the Modernized Metric System)
material exposed to the same radiation field. The procedure is
E665 Practice for Determining Absorbed Dose Versus
restricted to homogeneous materials composed of the elements
Depth in Materials Exposed to the X-Ray Output of Flash
for which absorption coefficients have been tabulated (2). It
5
X-Ray Machines
also requires some knowledge of the energy spectrum of the
E668 Practice for Application of Thermoluminescence-
radiation field produced by the source under consideration.
Dosimetry(TLD)SystemsforDeterminingAbsorbedDose
Generally, the accuracy of this method is limited by the
5
in Radiation-Hardness Testing of Electronic Devices
accuracy to which the energy spectrum of the radiation field is
E1249 Practice for Minimizing Dosimetry Errors in Radia-
known.
tion Hardness Testing of Silicon Electronic Devices Using
1.3 The results of this practice are only valid if charged
5
Co-60 Sources
particle equilibrium exists in the material and at the depth of
2.2 International Commission on Radiation Units and
interest. Thus, this practice is not applicable for determining
Measurements (ICRU) Reports:
absorbeddoseintheimmediatevicinityofboundariesbetween
ICRU Report 14—Radiation Dosimetry: X Rays and
materials of widely differing atomic numbers. For more infor-
Gamma Rays with Maximum Photon Energies Between
mation on this topic, see Practice E1249.
7
4 0.6 and 60 MeV
1.4 Energy transport computer codes exist that are formu-
ICRU Report 18—Specification of High Activity Gamma-
lated to calculate absorbed dose in materials more precisely
7
Ray Sources
than this method. To use these codes, more effort, time, and
ICRUReport21—Radiation Dosimetry:ElectronswithIni-
expense are required. If the situation warrants, such calcula-
7
tial Energies Between 1 and 50 MeV
tions should be used rather than the method described here.
7
ICRU Report 33—Radiation Quantities and Units
1.5 This standard does not purport to address all of the
7
ICRU Report 34—The Dosimetry of Pulsed Radiation
safety concerns, if any, associated with its use. It is the
3. Significance and Use
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
3.1 Theabsorbeddoseisamoremeaningfulparameterthan
Technology and Applications and is the direct responsibility of Subcommittee
exposure for use in relating the effects of radiation on materi-
E10.07 on Radiation Dosimetry for Radiation Effects on Materials and Devices.
als. It expresses the energy absorbed by the irradiated material
Current edition approved July 10, 2003. Published August 2003. Originally
approved in 1997. Last previous edition approved in 1997 as E666–97.
per unit mass, whereas exposure is related to the amount of
2
The boldface numbers in parentheses refer to the list of references appended to
charge produced in air per unit mass. Absorbed dose, as
this practice.
3
referred to here, implies that the measurement is made under
For calculation of absorbed dose in biological materials such as tissue or bone,
etc.,ICRUReport14providesmoreinformationandproceduresforamoreaccurate
calculation than this practice.
4
Information on and packages of computer codes can be obtained from The
5
Radiation Safety Information Computational Center, Oak Ridge National Labora- Annual Book of ASTM Standards, Vol 12.02.
6
tory, P.O. Box 2008, Oak Ridge, TN 37831-6362. This information center collects, Annual Book of ASTM Standards, Vol 14.02.
7
organizes, evaluates, and disseminates shielding
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