ASTM E2006-22
(Guide)Standard Guide for Benchmark Testing of Light Water Reactor Calculations
Standard Guide for Benchmark Testing of Light Water Reactor Calculations
SIGNIFICANCE AND USE
4.1 This guide deals with the difficult problem of benchmarking neutron transport calculations carried out to determine fluences for plant specific reactor geometries. The calculations are necessary for fluence determination in locations important for material radiation damage estimation and which are not accessible to measurement. Typically, the most important application of such calculations is the estimation of fluence within the reactor vessel of operating light water reactors (LWR) to provide accurate estimates of the irradiation embrittlement of the base and weld metal in the vessel. The benchmark procedure must not only prove that calculations give reasonable results but that their uncertainties are propagated with due regard to the sensitivities of the different input parameters used in the transport calculations. Benchmarking is achieved by building up data bases of benchmark experiments that have different influences on uncertainty propagation. For example, in simple vessel wall mockups where measurements are made within a simulated reactor vessel wall, the integral effect of uncertainties in iron cross sections (absorption and elastic and inelastic scattering) are dominant and have been bounded by the agreement between calculation and measurement. For more complicated integral benchmarks, other factors such as: uncertainties in the distribution of fission sources, geometry, the energy-dependent cross sections, and the angular scattering distribution for elemental components of major materials in the neutron field (such as water and iron) may all be important uncertainty contributors. This guide describes general procedures for using neutron fields with known characteristics to corroborate the calculational methodology and nuclear data used to derive neutron field information from measurements of neutron sensor response.
4.2 The bases for benchmark field referencing are usually irradiations performed in standard neutron fields with well-known energy spe...
SCOPE
1.1 This guide covers general approaches for benchmarking neutron transport calculations for pressure vessel surveillance programs in light water reactor systems. A companion guide (Guide E2005) covers use of benchmark fields for testing neutron transport calculations and cross sections in well controlled environments. This guide covers experimental benchmarking of neutron fluence calculations (or calculations of other exposure parameters such as dpa) in more complex geometries relevant to reactor pressure vessel surveillance. Particular sections of the guide discuss: the use of well-characterized benchmark neutron fields to provide an indication of the accuracy of the calculational methods and nuclear data when applied to typical cases; and the use of plant specific measurements to indicate bias in individual plant calculations. Use of these two benchmark techniques will serve to limit plant-specific calculational uncertainty, and, when combined with analytical uncertainty estimates for the calculations, will provide uncertainty estimates for reactor fluences with a higher degree of confidence.
1.2 Although this guide and the companion guide, Guide E2005, are focused on power reactors, the principle of this guide is also applicable to non-power light water reactor pressure vessel surveillance programs.
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: E2006 − 22
Standard Guide for
1
Benchmark Testing of Light Water Reactor Calculations
This standard is issued under the fixed designation E2006; 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
2.1 ASTM Standards:
1.1 This guide covers general approaches for benchmarking
E170 Terminology Relating to Radiation Measurements and
neutron transport calculations for pressure vessel surveillance
Dosimetry
programs in light water reactor systems. A companion guide
E261 Practice for Determining Neutron Fluence, Fluence
(Guide E2005) covers use of benchmark fields for testing
Rate, and Spectra by Radioactivation Techniques
neutron transport calculations and cross sections in well
E262 Test Method for Determining Thermal Neutron Reac-
controlled environments. This guide covers experimental
tion Rates and Thermal Neutron Fluence Rates by Radio-
benchmarking of neutron fluence calculations (or calculations
activation Techniques
of other exposure parameters such as dpa) in more complex
E706 MasterMatrixforLight-WaterReactorPressureVessel
geometries relevant to reactor pressure vessel surveillance.
Surveillance Standards
Particular sections of the guide discuss: the use of well-
E844 Guide for Sensor Set Design and Irradiation for
characterized benchmark neutron fields to provide an indica-
Reactor Surveillance
tion of the accuracy of the calculational methods and nuclear
E944 Guide for Application of Neutron Spectrum Adjust-
datawhenappliedtotypicalcases;andtheuseofplantspecific
ment Methods in Reactor Surveillance
measurements to indicate bias in individual plant calculations.
E1006 Practice for Analysis and Interpretation of Physics
Use of these two benchmark techniques will serve to limit
Dosimetry Results from Test Reactor Experiments
plant-specific calculational uncertainty, and, when combined
E1018 Guide for Application of ASTM Evaluated Cross
with analytical uncertainty estimates for the calculations, will
Section Data File
provideuncertaintyestimatesforreactorfluenceswithahigher
E2005 Guide for Benchmark Testing of Reactor Dosimetry
degree of confidence.
in Standard and Reference Neutron Fields
1.2 Although this guide and the companion guide, Guide
E2005, are focused on power reactors, the principle of this 3. Terminology
guide is also applicable to non-power light water reactor
3.1 Definitions—definitions of terms used in this guide may
pressure vessel surveillance programs.
be found in Terminology E170.
1.3 This standard does not purport to address all of the
4. Significance and Use
safety concerns, if any, associated with its use. It is the
responsibility of the user of this standard to establish appro-
4.1 This guide deals with the difficult problem of bench-
priate safety, health, and environmental practices and deter-
markingneutrontransportcalculationscarriedouttodetermine
mine the applicability of regulatory limitations prior to use.
fluences for plant specific reactor geometries. The calculations
are necessary for fluence determination in locations important
1.4 This international standard was developed in accor-
for material radiation damage estimation and which are not
dance with internationally recognized principles on standard-
accessible to measurement. Typically, the most important
ization established in the Decision on Principles for the
application of such calculations is the estimation of fluence
Development of International Standards, Guides and Recom-
within the reactor vessel of operating light water reactors
mendations issued by the World Trade Organization Technical
(LWR) to provide accurate estimates of the irradiation em-
Barriers to Trade (TBT) Committee.
brittlement of the base and weld metal in the vessel. The
benchmark procedure must not only prove that calculations
1
This guide 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, 2022. Published March 2022. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
approved in 1999. Last previous edition approved in 2016 as E2006 – 16. DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/E2006-22. the ASTM website.
Copyright © ASTM International, 10
...
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: E2006 − 16 E2006 − 22
Standard Guide for
1
Benchmark Testing of Light Water Reactor Calculations
This standard is issued under the fixed designation E2006; 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 guide covers general approaches for benchmarking neutron transport calculations for pressure vessel surveillance
programs in light water reactor systems. A companion guide (Guide E2005) covers use of benchmark fields for testing neutron
transport calculations and cross sections in well controlled environments. This guide covers experimental benchmarking of neutron
fluence calculations (or calculations of other exposure parameters such as dpa) in more complex geometries relevant to reactor
pressure vessel surveillance. Particular sections of the guide discuss: the use of well-characterized benchmark neutron fields to
provide an indication of the accuracy of the calculational methods and nuclear data when applied to typical cases; and the use of
plant specific measurements to indicate bias in individual plant calculations. Use of these two benchmark techniques will serve to
limit plant-specific calculational uncertainty, and, when combined with analytical uncertainty estimates for the calculations, will
provide uncertainty estimates for reactor fluences with a higher degree of confidence.
1.2 Although this guide and the companion guide, Guide E2005, are focused on power reactors, the principle of this guide is also
applicable to non-power light water reactor pressure vessel surveillance programs.
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 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.
2. Referenced Documents
2
2.1 ASTM Standards:
E170 Terminology Relating to Radiation Measurements and Dosimetry
E261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
E262 Test Method for Determining Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation
Techniques
E706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards
E844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance
E1006 Practice for Analysis and Interpretation of Physics Dosimetry Results from Test Reactor Experiments
E1018 Guide for Application of ASTM Evaluated Cross Section Data File
1
This test method 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 June 1, 2016Feb. 1, 2022. Published July 2016March 2022. Originally approved in 1999. Last previous edition approved in 20102016 as
E2006 – 10.E2006 – 16. DOI: 10.1520/E2006-16.
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.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
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E2006 − 22
E2005 Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
3. Terminology
3.1 Definitions—definitions of terms used in this guide may be found in Terminology E170.
4. Significance and Use
4.1 This guide deals with the difficult problem of benchmarking neutron transport calculations carried out to determine fluences
for plant specific reactor geometries. The calculations are necessary for fluence determination in locations important for material
radiation damage estimation and which are
...
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