ASTM E1006-02

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 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 2005E 2006and 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: 09-Jun-2002
• ICS: 17.240 - Radiation measurements
• Technical Committee: E10 - Nuclear Technology and Applications
• Drafting Committee: E10.05 - Nuclear Radiation Metrology

Relations

• Replaces: ASTM E1006-96 - Standard Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E 706(II)
• Effective Date: 10-Jun-2002
• Replaced By: ASTM E1006-08 - Standard Practice for Analysis and Interpretation of Physics Dosimetry Results for Test Reactors, E 706(II)
• 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: 10-Jun-2002
• Referred By: ASTM E2006-22 - Standard Guide for Benchmark Testing of Light Water Reactor Calculations
• Effective Date: 10-Jun-2002
• Referred By: ASTM E853-23 - Standard Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
• Effective Date: 10-Jun-2002

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:E1006–02
Standard Practice for
Analysis and Interpretation of Physics Dosimetry Results
1
for Test Reactors, E706(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 (e) indicates an editorial change since the last revision or reapproval.
1. Scope E 482 Guide forApplication of Neutron Transport Methods
,
2 3
for Reactor Vessel Surveillance, E 706 (IID)
1.1 This practice covers the methodology summarized in
E 560 Practice for Extrapolating Reactor Vessel Surveil-
Annex A1 to be used in the analysis and interpretation of
,
2 3
lance Dosimetry Results, E 706 (IC)
physics-dosimetry results from test reactors.
E 646 Test Method for Tensile Strain-Hardening Exponents
1.2 This practice relies on, and ties together, the application
4
(n-Values) of Metallic Sheet Materials
of several supporting ASTM standard practices, guides, and
E 693 Practice for Characterizing Neutron Exposures in
methods.
Iron and Low Alloy Steels in Terms of Displacements Per
1.3 Support subject areas that are discussed include reactor
2,3
Atom (DPA), E 706 (ID)
physics calculations, dosimeter selection and analysis, expo-
E 706 Master Matrix for Light-Water Reactor Pressure
sure units, and neutron spectrum adjustment methods.
3
Vessel Surveillance Standards, E 706 (O)
1.4 This practice is directed towards the development and
E 844 Guide for Sensor Set Design and Irradiation for
application of physics-dosimetry-metallurgical data obtained
,
2 3
Reactor Surveillance, E 706 (IIC)
from test reactor irradiation experiments that are performed in
E 853 Practice for Analysis and Interpretation of Light-
support of the operation, licensing, and regulation of LWR
,
2 3
Water Reactor Surveillance Results, E 706 (IA)
nuclear power plants. It specifically addresses the physics-
E 854 Test Method for Application and Analysis of Solid
dosimetry aspects of the problem. Procedures related to the
State Track Recorder (SSTR) Monitors for Reactor Sur-
analysis, interpretation, and application of both test and power
2,3
veillance, E 706 (IIIB)
reactor physics-dosimetry-metallurgy results are addressed in
E 900 Guide for Predicting Neutron Radiation Damage to
Practices E 185, E 560, E 853, and E 1035, Guides E 900,
2,3
Reactor Vessel Materials, E 706 (IIF)
E 2005E 2006and Test Method E 646.
E 910 Specification forApplication andAnalysis of Helium
1.5 This standard may involve hazardous materials, opera-
Accumulation Fluence Monitors for Reactor Vessel Sur-
tions, and equipment. This standard does not purport to
,
2 3
veillance, E 706 (IIIC)
address all of the safety concerns, if any, associated with its
E 944 Guide for Application of Neutron Spectrum Adjust-
use. It is the responsibility of the user of this standard to
,
2 3
ment Methods in Reactor Surveillance, E 706 (IIA)
establish appropriate safety and health practices and deter-
E 1005 Test Method forApplication andAnalysis of Radio-
mine the applicability of regulatory limitations prior to use.
metric Monitors for Reactor Vessel Surveillance, E 706
2,3
2. Referenced Documents
(IIIA)
E 1018 Guide for Application of ASTM Evaluated Cross
2.1 ASTM Standards:
2,3
Section Data File, E 706 (IIB)
E 185 Practice for Conducting Surveillance Tests for Light
E 1035 Practice for Determining Radiation Exposures for
Water-Cooled Nuclear Power Reactor Vessels, E 706
2
2,3
Nuclear Reactor Vessel Support Structures
(IF)
E 2005 Guide for the Benchmark Testing of Reactor Do-
simetry in Standard and Reference Neutron Field, E 706
1 2,3
This practice is under the jurisdiction of ASTM Committee E10 on Nuclear
(IIE-I)
Technology and Applications and is the direct responsibility of Subcommittee
E 2006 Guide for the Benchmark Testing of LWR Calcula-
E10.05 on Nuclear Radiation Metrology.
2,3
tions, E 706 (IIE-2)
Current edition approved June 10, 2002. Published September 2002. Originally
published as E 1006 – 84. Last previous edition E 1006 – 96. 2.2 Nuclear Regulatory Documents:
2
The reference in parentheses refers to Section 5 as well as to Figs. 1 and 2 of
Matrix E 706.
3 4
Annual Book of ASTM Standards, Vol 12.02. Annual Book of ASTM Standards, Vol 03.01.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
E1006–02
Code of Federal Regulations, “Fracture Toughness Require-
n(E) = number of neutrons per fission,
5
ments,” Chapter 10, Part 50, Appendix G
( = macroscopic fission cross section, and
f
Code of Federal Regulations, “Reactor Vessel Materials
f = fluence rate.
Surveillance Program Requirements,”
...