ASTM E482-22
(Guide)Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
Standard Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
SIGNIFICANCE AND USE
3.1 General:
3.1.1 The methodology recommended in this guide specifies criteria for validating computational methods and outlines procedures applicable to pressure vessel related neutronics calculations for test and power reactors. The material presented herein is useful for validating computational methodology and for performing neutronics calculations that accompany reactor vessel surveillance dosimetry measurements (see Master Matrix E706 and Practice E853). Briefly, the overall methodology involves: (1) methods-validation calculations based on at least one well-documented benchmark problem, and (2) neutronics calculations for the facility of interest. The neutronics calculations of the facility of interest and of the benchmark problem should be performed consistently, with important modeling parameters kept the same or as similar as is feasible. In particular, the same energy group structure and common broad-group microscopic cross sections should be used for both problems. Further, the benchmark problem should be characteristically similar to the facility of interest. For example, a power reactor benchmark should be utilized for power reactor calculations. Non-power reactors may have special features that may affect pressure vessel fluence and require consideration when developing a benchmark, such as beam tubes, irradiation facilities, and non-core neutron sources. The neutronics calculations involve two tasks: (1) determination of the neutron source distribution in the reactor core by utilizing diffusion theory (or transport theory) calculations in conjunction with reactor power distribution measurements, and (2) performance of a fixed fission rate neutron source (fixed-source) transport theory calculation to determine the neutron fluence rate distribution in the reactor core, through the internals and in the pressure vessel. Some neutronics modeling details for the benchmark, test reactor, or the power reactor calculation will differ; therefore, the proc...
SCOPE
1.1 Need for Neutronics Calculations—An accurate calculation of the neutron fluence and fluence rate at several locations is essential for the analysis of integral dosimetry measurements and for predicting irradiation damage exposure parameter values in the pressure vessel. Exposure parameter values may be obtained directly from calculations or indirectly from calculations that are adjusted with dosimetry measurements; Guide E944 and Practice E853 define appropriate computational procedures.
1.2 Methodology—Neutronics calculations for application to reactor vessel surveillance encompass three essential areas: (1) validation of methods by comparison of calculations with dosimetry measurements in a benchmark experiment, (2) determination of the neutron source distribution in the reactor core, and (3) calculation of neutron fluence rate at the surveillance position and in the pressure vessel.
1.3 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.
1.4 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.
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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: E482 − 22
Standard Guide for
Application of Neutron Transport Methods for Reactor
1
Vessel Surveillance
This standard is issued under the fixed designation E482; 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 and Low Alloy Steels in Terms of Displacements Per
Atom (DPA)
1.1 Need for Neutronics Calculations—An accurate calcu-
E706 MasterMatrixforLight-WaterReactorPressureVessel
lation of the neutron fluence and fluence rate at several
Surveillance Standards
locations is essential for the analysis of integral dosimetry
E844 Guide for Sensor Set Design and Irradiation for
measurements and for predicting irradiation damage exposure
Reactor Surveillance
parameter values in the pressure vessel. Exposure parameter
E853 Practice forAnalysis and Interpretation of Light-Water
values may be obtained directly from calculations or indirectly
Reactor Surveillance Neutron Exposure Results
from calculations that are adjusted with dosimetry measure-
E944 Guide for Application of Neutron Spectrum Adjust-
ments; Guide E944 and Practice E853 define appropriate
ment Methods in Reactor Surveillance
computational procedures.
E1018 Guide for Application of ASTM Evaluated Cross
1.2 Methodology—Neutronics calculations for application
Section Data File
to reactor vessel surveillance encompass three essential areas:
E2006 Guide for Benchmark Testing of Light Water Reactor
(1) validation of methods by comparison of calculations with
Calculations
dosimetry measurements in a benchmark experiment, (2)
3
2.2 Nuclear Regulatory Documents:
determination of the neutron source distribution in the reactor
NUREG/CR-1861 LWR Pressure Vessel Surveillance Do-
core, and (3) calculation of neutron fluence rate at the surveil-
simetry Improvement Program: PCA Experiments and
lance position and in the pressure vessel.
Blind Test
1.3 This standard does not purport to address all of the
NUREG/CR-3318 LWR Pressure Vessel Surveillance Do-
safety concerns, if any, associated with its use. It is the
simetry Improvement Program: PCA Experiments, Blind
responsibility of the user of this standard to establish appro-
Test, and Physics-Dosimetry Support for the PSF Experi-
priate safety, health, and environmental practices and deter-
ments
mine the applicability of regulatory limitations prior to use.
NUREG/CR-3319 LWR Pressure Vessel Surveillance Do-
1.4 This international standard was developed in accor-
simetry Improvement Program: LWR Power Reactor Sur-
dance with internationally recognized principles on standard-
veillance Physics-Dosimetry Data Base Compendium
ization established in the Decision on Principles for the
NUREG/CR-5049 Pressure Vessel Fluence Analysis and
Development of International Standards, Guides and Recom-
Neutron Dosimetry
mendations issued by the World Trade Organization Technical
Barriers to Trade (TBT) Committee. 3. Significance and Use
3.1 General:
2. Referenced Documents
3.1.1 Themethodologyrecommendedinthisguidespecifies
2
2.1 ASTM Standards:
criteria for validating computational methods and outlines
E693 Practice for Characterizing Neutron Exposures in Iron
procedures applicable to pressure vessel related neutronics
calculationsfortestandpowerreactors.Thematerialpresented
herein is useful for validating computational methodology and
1
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear
for performing neutronics calculations that accompany reactor
Technology and Applications and is the direct responsibility of Subcommittee
vessel surveillance dosimetry measurements (see Master Ma-
E10.05 on Nuclear Radiation Metrology.
Current edition approved July 1, 2022. Published July 2022. Originally approved
trix E706 and Practice E853). Briefly, the overall methodology
in 1976. Last previous edition approved in 2016 as E482 – 16. DOI: 10.1520/
involves: (1) methods-validation calculations based on at least
E0482-22.
2
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
3
Standards volume information, refer to the standard’s Document Summary page on Available from Superintendent of Documents, U.S. Government Printing
the ASTM website. Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E482 − 22
one wel
...
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: E482 − 16 E482 − 22
Standard Guide for
Application of Neutron Transport Methods for Reactor
1
Vessel Surveillance
This standard is issued under the fixed designation E482; 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 Need for Neutronics Calculations—An accurate calculation of the neutron fluence and fluence rate at several locations is
essential for the analysis of integral dosimetry measurements and for predicting irradiation damage exposure parameter values in
the pressure vessel. Exposure parameter values may be obtained directly from calculations or indirectly from calculations that are
adjusted with dosimetry measurements; Guide E944 and Practice E853 define appropriate computational procedures.
1.2 Methodology—Neutronics calculations for application to reactor vessel surveillance encompass three essential areas: (1)
validation of methods by comparison of calculations with dosimetry measurements in a benchmark experiment, (2) determination
of the neutron source distribution in the reactor core, and (3) calculation of neutron fluence rate at the surveillance position and
in the pressure vessel.
1.3 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 requirementslimitations prior to use.
1.4 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:
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
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
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
E1018 Guide for Application of ASTM Evaluated Cross Section Data File
E2006 Guide for Benchmark Testing of Light Water Reactor Calculations
3
2.2 Nuclear Regulatory Documents:
NUREG/CR-1861 LWR Pressure Vessel Surveillance Dosimetry Improvement Program: PCA Experiments and Blind Test
1
This guide 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 July 1, 2016July 1, 2022. Published August 2016July 2022. Originally approved in 1976. Last previous edition approved in 20112016 as
ɛ1
E482 – 11E482 – 16. . DOI: 10.1520/E0482-16.10.1520/E0482-22.
2
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 Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
3
Available from Superintendent of Documents, U.S. Government Printing Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
E482 − 22
NUREG/CR-3318 LWR Pressure Vessel Surveillance Dosimetry Improvement Program: PCA Experiments, Blind Test, and
Physics-Dosimetry Support for the PSF Experiments
NUREG/CR-3319 LWR Pressure Vessel Surveillance Dosimetry Improvement Program: LWR Power Reactor Surveillance
Physics-Dosimetry Data Base Compendium
NUREG/CR-5049 Pressure Vessel Fluence Analysis and Neutron Dosimetry
3. Significance and Use
3.1 General:
3.1.1 The methodology recommended in this guide specifies criteria for validating computational methods and outlines procedures
applicable to pressure vessel related neutronics calculations for test and power reactors. The material presented herein is useful for
validating computational methodology and for performing neutronics calculations that acc
...
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