ASTM E1006-21
(Practice)Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
Standard Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
SIGNIFICANCE AND USE
3.1 The mechanical properties of steels and other metals are altered by exposure to neutron radiation. These property changes are assumed to be a function of chemical composition, metallurgical condition, temperature, fluence (perhaps also fluence rate), and neutron spectrum. The influence of these variables is not completely understood. The functional dependency between property changes and neutron radiation is summarized in the form of damage exposure parameters that are weighted integrals over the neutron fluence spectrum.
3.2 The evaluation of neutron radiation effects on pressure vessel steels and the determination of safety limits requires the knowledge of uncertainties in the prediction of radiation exposure parameters (for example, dpa (Practice E693), neutron fluence greater than 1.0 MeV, neutron fluence greater than 0.1 MeV, thermal neutron fluence, etc.). This practice describes recommended procedures and data for determining these exposure parameters (and the associated uncertainties) for test reactor experiments.
3.3 The nuclear industry draws much of its information from databases that come from test reactor experiments. Therefore, it is essential that reliable databases are obtained from test reactors to assess safety issues in Light Water Reactor (LWR) nuclear power plants.
SCOPE
1.1 This practice covers the methodology summarized in Annex A1 to be used in the analysis and interpretation of physics-dosimetry results from test reactors.
1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods.
1.3 Support subject areas that are discussed include reactor physics calculations, dosimeter selection and analysis, exposure units, and neutron spectrum adjustment methods.
1.4 This practice is directed towards the development and application of physics-dosimetry-metallurgical data obtained from test reactor irradiation experiments that are performed in support of the operation, licensing, and regulation of LWR nuclear power plants. It specifically addresses the physics-dosimetry aspects of the problem. Procedures related to the analysis, interpretation, and application of both test and power reactor physics-dosimetry-metallurgy results are addressed in Practices E185, E853, and E1035, Guides E900, E2005, E2006 and Test Method E646. See also E706.
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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.
1.6 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.
General Information
Relations
Buy Standard
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: E1006 − 21
Standard Practice for
Analysis and Interpretation of Physics Dosimetry Results
1
from Test Reactor Experiments
This standard is issued under the fixed designation E1006; 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 2. Referenced Documents
2
1.1 This practice covers the methodology summarized in 2.1 ASTM Standards:
Annex A1 to be used in the analysis and interpretation of E185 Practice for Design of Surveillance Programs for
physics-dosimetry results from test reactors. Light-Water Moderated Nuclear Power Reactor Vessels
E482 Guide for Application of Neutron Transport Methods
1.2 This practice relies on, and ties together, the application
for Reactor Vessel Surveillance
of several supporting ASTM standard practices, guides, and
E646 Test Method for Tensile Strain-Hardening Exponents
methods.
(n -Values) of Metallic Sheet Materials
1.3 Support subject areas that are discussed include reactor
E693 Practice for Characterizing Neutron Exposures in Iron
physics calculations, dosimeter selection and analysis, expo-
and Low Alloy Steels in Terms of Displacements Per
sure units, and neutron spectrum adjustment methods.
Atom (DPA)
E706 MasterMatrixforLight-WaterReactorPressureVessel
1.4 This practice is directed towards the development and
application of physics-dosimetry-metallurgical data obtained Surveillance Standards
E844 Guide for Sensor Set Design and Irradiation for
from test reactor irradiation experiments that are performed in
support of the operation, licensing, and regulation of LWR Reactor Surveillance
E853 Practice forAnalysis and Interpretation of Light-Water
nuclear power plants. It specifically addresses the physics-
dosimetry aspects of the problem. Procedures related to the Reactor Surveillance Neutron Exposure Results
E854 Test Method for Application and Analysis of Solid
analysis, interpretation, and application of both test and power
reactor physics-dosimetry-metallurgy results are addressed in State Track Recorder (SSTR) Monitors for Reactor Sur-
PracticesE185,E853,andE1035,GuidesE900,E2005,E2006 veillance
E900 Guide for Predicting Radiation-Induced Transition
and Test Method E646. See also E706.
Temperature Shift in Reactor Vessel Materials
1.5 This standard does not purport to address all of the
E910 Test Method for Application and Analysis of Helium
safety concerns, if any, associated with its use. It is the
Accumulation Fluence Monitors for Reactor Vessel Sur-
responsibility of the user of this standard to establish appro-
veillance
priate safety, health, and environmental practices and deter-
E944 Guide for Application of Neutron Spectrum Adjust-
mine the applicability of regulatory limitations prior to use.
ment Methods in Reactor Surveillance
1.6 This international standard was developed in accor-
E1005 Test Method for Application and Analysis of Radio-
dance with internationally recognized principles on standard-
metric Monitors for Reactor Vessel Surveillance
ization established in the Decision on Principles for the
E1018 Guide for Application of ASTM Evaluated Cross
Development of International Standards, Guides and Recom-
Section Data File
mendations issued by the World Trade Organization Technical
E1035 Practice for Determining Neutron Exposures for
Barriers to Trade (TBT) Committee.
Nuclear Reactor Vessel Support Structures
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applications and is the direct responsibility of Subcommittee
2
E10.05 on Nuclear Radiation Metrology. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved Feb. 1, 2021. Published March 2021. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
approved in 1984. Last previous edition approved in 2013 as E1006 – 13. DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/E1006-21. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E1006 − 21
E2005 Guide for Benchmark Testing of Reactor Dosimetry reactors. Complex geometries can be handled in 3D space
in Standard and Reference Neutron Fields using the Monte Carlo approach.
E2006 Guide for Benchmark Testing of Light Water Reactor
4.2 Determination of Core Fission Source Distribu
...
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: E1006 − 13 E1006 − 21
Standard Practice for
Analysis and Interpretation of Physics Dosimetry Results
1
from Test Reactor Experiments
This standard is issued under the fixed designation E1006; 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 practice covers the methodology summarized in Annex A1 to be used in the analysis and interpretation of
physics-dosimetry results from test reactors.
1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods.
1.3 Support subject areas that are discussed include reactor physics calculations, dosimeter selection and analysis, exposure units,
and neutron spectrum adjustment methods.
1.4 This practice is directed towards the development and application of physics-dosimetry-metallurgical data obtained from test
reactor irradiation experiments that are performed in support of the operation, licensing, and regulation of LWR nuclear power
plants. It specifically addresses the physics-dosimetry aspects of the problem. Procedures related to the analysis, interpretation, and
application of both test and power reactor physics-dosimetry-metallurgy results are addressed in Practices E185, E853, and E1035,
Guides E900, E2005, E2006 and Test Method E646. See also E706.
1.5 This standard may involve hazardous materials, operations, and equipment. 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 safety, health, and healthenvironmental practices and determine the applicability of regulatory limitations prior to use.
1.6 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.
2. Referenced Documents
2
2.1 ASTM Standards:
E185 Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
E646 Test Method for Tensile Strain-Hardening Exponents (n -Values) of Metallic Sheet Materials
E693 Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA)
E706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
1
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.05 on
Nuclear Radiation Metrology.
Current edition approved June 1, 2013Feb. 1, 2021. Published July 2013March 2021. Originally approved in 1984. Last previous edition approved in 20082013 as
E1006 – 08.E1006 – 13. DOI: 10.1520/E1006-13.10.1520/E1006-21.
2
The reference in parentheses refers For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org.
For Annual Book of ASTM Standardsto Section 5 as well as to Figs. 1 and 2 of Matrix volume information, refer to the standard’s Document Summary page on the ASTM
website.E706.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E1006 − 21
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance
E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
E854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance
E900 Guide for Predicting Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials
E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
E1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance
E1018 Guide for Application of ASTM Evaluated Cross Section Data File
E1035 Practice for Determin
...
Questions, Comments and Discussion
Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.