ASTM E1006-08

Standard Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E 706(II)

SIGNIFICANCE AND USE
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.
The evaluation of neutron radiation effects on pressure vessel steels and the determination of safety limits require the knowlege of uncertainties in the prediction of radiation exposure parameters (for example, dpa (Practice E 693), 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.
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 E 185, E 560, E 853, and E 1035, Guides E 900, E 2005, E 2006 and Test Method E 646.
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 and health practices and determine the applicability of regulatory limitations prior to use.

General Information

• Status: Historical
• Publication Date: 31-Oct-2008
• ICS: 17.240 - Radiation measurements
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.05 - Nuclear Radiation Metrology

Relations

• Replaces: ASTM E1006-02 - Standard Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E 706(II)
• Effective Date: 01-Nov-2008
• Referred By: ASTM E853-23 - Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
• Effective Date: 01-Nov-2008
• Referred By: ASTM E1297-18 - Standard Test Method for Measuring Fast-Neutron Reaction Rates by Radioactivation of Niobium
• Effective Date: 01-Nov-2008
• Referred By: ASTM E2006-22 - Standard Guide for Benchmark Testing of Light Water Reactor Calculations
• Effective Date: 01-Nov-2008

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: E1006 − 08
StandardPractice for
Analysis and Interpretation of Physics Dosimetry Results
1
for Test Reactors, E 706(II)
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 E560 Practice for Extrapolating Reactor Vessel Surveillance
3
Dosimetry Results, E 706(IC) (Withdrawn 2009)
1.1 This practice covers the methodology summarized in
E646 Test Method for Tensile Strain-Hardening Exponents
Annex A1 to be used in the analysis and interpretation of
(n -Values) of Metallic Sheet Materials
physics-dosimetry results from test reactors.
E693 Practice for Characterizing Neutron Exposures in Iron
1.2 This practice relies on, and ties together, the application
and Low Alloy Steels in Terms of Displacements Per
of several supporting ASTM standard practices, guides, and
Atom (DPA), E 706(ID)
methods.
E706 MasterMatrixforLight-WaterReactorPressureVessel
3
1.3 Support subject areas that are discussed include reactor Surveillance Standards, E 706(0) (Withdrawn 2011)
E844 Guide for Sensor Set Design and Irradiation for
physics calculations, dosimeter selection and analysis, expo-
sure units, and neutron spectrum adjustment methods. Reactor Surveillance, E 706 (IIC)
E853 Practice forAnalysis and Interpretation of Light-Water
1.4 This practice is directed towards the development and
Reactor Surveillance Results, E706(IA)
application of physics-dosimetry-metallurgical data obtained
E854 Test Method for Application and Analysis of Solid
from test reactor irradiation experiments that are performed in
State Track Recorder (SSTR) Monitors for Reactor
support of the operation, licensing, and regulation of LWR
Surveillance, E706(IIIB)
nuclear power plants. It specifically addresses the physics-
E900 Guide for Predicting Radiation-Induced Transition
dosimetry aspects of the problem. Procedures related to the
Temperature Shift in Reactor Vessel Materials, E706 (IIF)
analysis, interpretation, and application of both test and power
E910 Test Method for Application and Analysis of Helium
reactor physics-dosimetry-metallurgy results are addressed in
Accumulation Fluence Monitors for Reactor Vessel
Practices E185, E560, E853, and E1035, Guides E900, E2005,
Surveillance, E706 (IIIC)
E2006 and Test Method E646.
E944 Guide for Application of Neutron Spectrum Adjust-
1.5 This standard may involve hazardous materials,
ment Methods in Reactor Surveillance, E 706 (IIA)
operations, and equipment. This standard does not purport to
E1005 Test Method for Application and Analysis of Radio-
address all of the safety concerns, if any, associated with its
metric Monitors for Reactor Vessel Surveillance, E 706
use. It is the responsibility of the user of this standard to
(IIIA)
establish appropriate safety and health practices and deter-
E1018 Guide for Application of ASTM Evaluated Cross
mine the applicability of regulatory limitations prior to use.
Section Data File, Matrix E706 (IIB)
E1035 Practice for Determining Neutron Exposures for
2. Referenced Documents
Nuclear Reactor Vessel Support Structures
2
2.1 ASTM Standards:
E2005 Guide for Benchmark Testing of Reactor Dosimetry
E185 Practice for Design of Surveillance Programs for
in Standard and Reference Neutron Fields
Light-Water Moderated Nuclear Power Reactor Vessels
E2006 Guide for Benchmark Testing of Light Water Reactor
E482 Guide for Application of Neutron Transport Methods
Calculations
for Reactor Vessel Surveillance, E706 (IID)
2.2 Nuclear Regulatory Documents:
Code of Federal Regulations, “Fracture Toughness
4
1
Requirements,” Chapter 10, Part 50, Appendix G
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
Technology and Applicationsand is the direct responsibility of Subcommittee
E10.05 on Nuclear Radiation Metrology.
Current edition approved Nov. 1, 2008. Published December 2008. Originally
3
approved in 1984. Last previous edition approved in 2002 as E1006 – 02. DOI: The last approved version of this historical standard is referenced on
10.1520/E1006-08. www.astm.org.
2 4
The reference in parentheses refers to Section 5 as well as to Figs. 1 and 2 of Available from Superintendent of Documents, U.S. Government Printing
Matrix E706. Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
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E1006 − 08
Code of Federal Regulations, “Reactor Vessel Materials where:
Surveillance Program Requirements,” Chapter 10, Part
ν(E) = number of neutrons
...

This document is not anASTM standard and is intended only to provide the user of anASTM 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:E1006–02 Designation: E 1006 – 08
Standard Practice for
Analysis and Interpretation of Physics Dosimetry Results
1
for Test Reactors, E 706(II)
This standard is issued under the fixed designation E 1006; 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.Itspecificallyaddressesthephysics-dosimetryaspectsoftheproblem.Proceduresrelatedtotheanalysis,interpretation,and
applicationofbothtestandpowerreactorphysics-dosimetry-metallurgyresultsareaddressedinPracticesE 185,E 560,E 853,and
E 1035, Guides E 900, E 2005E2006, E 2006 and Test Method E 646.
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 and health practices and determine the applicability of regulatory limitations prior to use.
2. Referenced Documents
2
2.1 ASTM Standards:
,
E 185Practice for Conducting Surveillance Tests for Light Water-Cooled Nuclear Power Reactor Vessels, E706 (IF) Practice
for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
3
E 482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID),
,
2 3
E 560 Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results, E706 (IC) E 706(IC)
E 646 Test Method for Tensile Strain-Hardening Exponents (n-Values) of Metallic Sheet Materials
E 693 PracticeforCharacterizingNeutronExposuresinIronandLowAlloySteelsinTermsofDisplacementsPerAtom(DPA),
2,3
E706 (ID) E 706(ID)
3
E 706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706 (O) E 706(0)
2,3
E 844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E706 (IIC) E 706(IIC)
,
2 3
E 853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706 (IA) E706(IA)
E 854 TestMethodforApplicationandAnalysisofSolidStateTrackRecorder(SSTR)MonitorsforReactorSurveillance,E706
,
2 3
(IIIB) E706(IIIB)
2,3
E 900Guide for Predicting Neutron Radiation Damage to Reactor Vessel Materials, E706 (IIF) Guide for Predicting
Radiation-Induced Transition Temperature Shift in Reactor Vessel Materials, E706 (IIF)
E 910Specification Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel
3
Surveillance, E706 (IIIC),
3
E 944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA),
2,3
E 1005 Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E706 (IIIA) E
706(IIIA)
3
E 1018 Guide for Application of ASTM Evaluated Cross Section Data File, E706 Matrix E 706 (IIB),
E 1035 Practice for Determining RadiationNeutron Exposures for 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 E10.05 on
Nuclear Radiation Metrology.
Current edition approved June 10, 2002. Published September 2002. Originally published as E1006–84. Last previous edition E1006–96.
Current edition approved Nov. 1, 2008. Published December 2008. Originally approved in 1984. Last previous edition approved in 2002 as E 1006 – 02.
2
The reference in parentheses refers to Section 5 as well as to Figs. 1 and 2 of Matrix E 706.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

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