ASTM E2006-10
(Guide)Standard Guide for Benchmark Testing of Light Water Reactor Calculations
Standard Guide for Benchmark Testing of Light Water Reactor Calculations
SIGNIFICANCE AND USE
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. The most important application of such calculations is the estimation of fluence within the reactor vessel of operating power plants 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, fission spectra are the fundamental data bases which control propagation of cross section uncertainties, while such physics-dosimetry experiments as vessel wall mockups, where measurements are made within a simulated reactor vessel wall, control error propagation associated with geometrical and methods approximations in the transport calculations. 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.
The bases for benchmark field referencing are usually irradiations performed in standard neutron fields with well-known energy spectra and intensities. There are, however, less well known neutron fields that have been designed to mockup special environments, such as pressure vessel mockups in which it is possible to make dosimetry measurements inside of the steel volume of the “vessel”. When such mockups are suitably characterized they are also refer...
SCOPE
1.1 This guide covers general approaches for benchmarking neutron transport calculations 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 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 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.
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Designation: E2006 − 10
StandardGuide 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.
3
1. Scope Surveillance Standards, E 706(0) (Withdrawn 2011)
E844 Guide for Sensor Set Design and Irradiation for
1.1 This guide covers general approaches for benchmarking
Reactor Surveillance, E 706 (IIC)
neutron transport calculations in light water reactor systems.A
E944 Guide for Application of Neutron Spectrum Adjust-
companion guide (Guide E2005) covers use of benchmark
ment Methods in Reactor Surveillance, E 706 (IIA)
fields for testing neutron transport calculations and cross
E1018 Guide for Application of ASTM Evaluated Cross
sections in well controlled environments. This guide covers
Section Data File, Matrix E706 (IIB)
experimental benchmarking of neutron fluence calculations (or
E2005 Guide for Benchmark Testing of Reactor Dosimetry
calculations of other exposure parameters such as dpa) in more
in Standard and Reference Neutron Fields
complex geometries relevant to reactor surveillance. Particular
sections of the guide discuss: the use of well-characterized
3. Significance and Use
benchmark neutron fields to provide an indication of the
3.1 This guide deals with the difficult problem of bench-
accuracy of the calculational methods and nuclear data when
markingneutrontransportcalculationscarriedouttodetermine
applied to typical cases; and the use of plant specific measure-
fluences for plant specific reactor geometries. The calculations
ments to indicate bias in individual plant calculations. Use of
are necessary for fluence determination in locations important
these two benchmark techniques will serve to limit plant-
for material radiation damage estimation and which are not
specific calculational uncertainty, and, when combined with
accessible to measurement. The most important application of
analytical uncertainty estimates for the calculations, will pro-
such calculations is the estimation of fluence within the reactor
vide uncertainty estimates for reactor fluences with a higher
vessel of operating power plants to provide accurate estimates
degree of confidence.
of the irradiation embrittlement of the base and weld metal in
1.2 This standard does not purport to address all of the
the vessel. The benchmark procedure must not only prove that
safety concerns, if any, associated with its use. It is the
calculations give reasonable results but that their uncertainties
responsibility of the user of this standard to establish appro-
are propagated with due regard to the sensitivities of the
priate safety and health practices and determine the applica-
different input parameters used in the transport calculations.
bility of regulatory limitations prior to use.
Benchmarking is achieved by building up data bases of
benchmark experiments that have different influences on un-
2. Referenced Documents
certainty propagation. For example, fission spectra are the
2
2.1 ASTM Standards:
fundamental data bases which control propagation of cross
E261 Practice for Determining Neutron Fluence, Fluence
section uncertainties, while such physics-dosimetry experi-
Rate, and Spectra by Radioactivation Techniques
ments as vessel wall mockups, where measurements are made
E262 Test Method for Determining Thermal Neutron Reac-
within a simulated reactor vessel wall, control error propaga-
tion Rates and Thermal Neutron Fluence Rates by Radio-
tion associated with geometrical and methods approximations
activation Techniques
in the transport calculations. This guide describes general
E706 MasterMatrixforLight-WaterReactorPressureVessel
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
1
This test method is under the jurisdiction ofASTM Committee E10 on Nuclear neutron sensor response.
Technology and Applicationsand is the direct responsibility of Subcommittee
3.2 The bases for benchmark field referencing are usually
E10.05 on Nuclear Radiation Metrology.
Current edition approved Oct. 1, 2010. Published October 2010. Originally irradiations performed in standard neutron fields with well-
approved in 1999. Last previous edition approved in 2005 as E2006 - 05. DOI:
known energy spectra and intensities. There are, however, less
10.1520/E2006-10.
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
Standard
...
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:E 2006–99 Designation:E2006–10
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 (ϵ) indicates an editorial change since the last revision or reapproval.
1. Scope
1.1 This guide covers general approaches for benchmarking neutron transport calculations in light water reactor systems. A
companion guide (Guide E 706–IIE1)E 706E2005) 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 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 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
2.1 ASTM Standards:
2
E170Terminology Relating to Radiation Measurements and Dosimetry
E261 Practice for Determining Neutron Fluence, Fluence Rate, Fluence, and Spectra by Radioactivation Techniques
2
E262 Test Method for Determining Thermal Neutron Reaction and Fluence Rates by Radioactivation Techniques
2
E482Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E 706 (IID)
2
E560Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results, E 706 (IC) Test Method for Determining
Thermal Neutron Reaction Rates and Thermal Neutron Fluence Rates by Radioactivation Techniques
2
E706 MasterMatrixforLightWaterReactorPressureVesselSurveillanceStandards,E706(O) MasterMatrixforLight-Water
Reactor Pressure Vessel Surveillance Standards, E 706(0)
2
E844 Guide for Sensor Set Design and Irritation for Reactor Surveillance
2
E853Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E 706 (IA)
E854Test Method forApplication andAnalysis of Solid StateTrack Recorder (SSTR) Monitors for Reactor Surveillance, E 706
2
(IIB)
E910Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance, E
2
706 (IIIC) Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706 (IIC)
2
E944 Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
2
E1006Practice forAnalysis and Interpretation of Physics Dosimetry Results forTest Reactors, E 706 (II) Guide forApplication
of Neutron Spectrum Adjustment Methods in Reactor Surveillance, E 706 (IIA)
2
E1018 Guide for Application of ASTM Evaluated Cross Section Data File, E 706 (IIB) Guide for Application of ASTM
Evaluated Cross Section Data File, Matrix E706 (IIB)
E2005 Guide for Benchmark Testing of Reactor Dosimetry in Standard and Reference Neutron Fields
3. Significance and Use
3.1 This guide deals with the difficult problem of benchmarking neutron transport calculations carried out to determine fluences
1
ThistestmethodisunderthejurisdictionofASTMCommitteeE-10E10onNuclearTechnologyandApplicationsandisthedirectresponsibilityofSubcommitteeE10.05
on Nuclear Radiation and Metrology.
Current edition approved Feb. 10, 1999. Published April 1999.on Nuclear Radiation Metrology.
Current edition approved Oct. 1, 2010. Published October 2010. Originally approved in 1999. Last previous edition approved in 2005 as E2006 - 05. DOI:
10.1520/E2006-10.
2
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
, Vol 12.02.volume information, refer to the standard’s Document Sum
...
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