ASTM E1018-20
(Guide)Standard Guide for Application of ASTM Evaluated Cross Section Data File
Standard Guide for Application of ASTM Evaluated Cross Section Data File
SIGNIFICANCE AND USE
4.1 The ENDF/B library in the United States and similar libraries elsewhere, such as JEFF (23), JENDL (21), and BROND (22), provide a compilation of neutron cross section and other nuclear data for use by the nuclear community. The availability of these excellent evaluations makes possible standardized usage, thereby allowing easy referencing and intercomparisons of calculations. However, as the first ENDF/B files were developed it became apparent that they were not adequate for all applications. This need resulted in the development of the specialized ENDF/B Dosimetry File (17, 25), consisting of activation cross sections important for dosimetry applications. This file was made available worldwide. Later, other “Special Purpose” files were introduced (26). In the ENDF/B-VI compilation (27), dosimetry files no longer appeared as separate evaluation files. The ENDF/B-VII.0 compilation (28) removed most of the reaction-specific covariance files used by the dosimetry community. It kept the covariance files for the “standard cross sections” in a special sub-library, but the covariance data in this sub-library are only provided over the energy range in which each reaction is considered to be a “standard”, and does not include the full energy range required for LWR PVS dosimetry applications. Later updates to the ENDF/B releases added covariance files for some reaction channels but these covariance files were often based solely on calculations and were not representative of the methodology used to derive the underlying ENDF/B cross section. In response to the need for a dosimetry-specific library, the International Atomic Energy Agency convened a Coordinated Research Project (CRP) that drew upon the set of international experts to provide a recommended set of dosimetry cross sections and to compile a set of validation evidence that supported the use of this recommended dataset. This file, the International Reactor Dosimetry and Fusion File (IRDFF) (19, 20), draws upon oth...
SCOPE
1.1 This guide covers the establishment and use of an ASTM evaluated nuclear data cross section and uncertainty file for analysis of single or multiple sensor measurements in neutron fields related to light water reactor LWR-Pressure Vessel Surveillance (PVS). These fields include in- and ex-vessel surveillance positions in operating power reactors, benchmark fields, and reactor test regions.
1.2 Requirements for establishment of ASTM-recommended cross section files address data format, evaluation requirements, validation in benchmark fields, evaluation of error estimates (covariance file), and documentation. A further requirement for components of the ASTM-recommended cross section file is their internal consistency when combined with sensor measurements and used to determine a neutron spectrum.
1.3 Specifications for use include energy region of applicability, data processing requirements, and application of uncertainties.
1.4 This guide is directly related to and should be used primarily in conjunction with Guides E482 and E944, and Practices E560, E185, and E693.
1.5 The ASTM cross section and uncertainty file represents a generally available data set for use in sensor set analysis. However, the availability of this data set does not preclude the use of other validated data, either proprietary or nonproprietary. When alternate cross section files that deviate from the requirements laid out in this standard are used, the deviations should be noted to the customer of the dosimetry application.
1.6 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.
1.7 This international standard was developed in accordance with internationally recognized principles on standar...
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Designation: E1018 − 20
Standard Guide for
1
Application of ASTM Evaluated Cross Section Data File
This standard is issued under the fixed designation E1018; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope ization established in the Decision on Principles for the
Development of International Standards, Guides and Recom-
1.1 This guide covers the establishment and use of an
mendations issued by the World Trade Organization Technical
ASTMevaluatednucleardatacrosssectionanduncertaintyfile
Barriers to Trade (TBT) Committee.
for analysis of single or multiple sensor measurements in
neutron fields related to light water reactor LWR-Pressure
2. Referenced Documents
Vessel Surveillance (PVS). These fields include in- and ex-
2
2.1 ASTM Standards:
vessel surveillance positions in operating power reactors,
E170Terminology Relating to Radiation Measurements and
benchmark fields, and reactor test regions.
Dosimetry
1.2 Requirements for establishment of ASTM-
E185Practice for Design of Surveillance Programs for
recommended cross section files address data format, evalua-
Light-Water Moderated Nuclear Power Reactor Vessels
tionrequirements,validationinbenchmarkfields,evaluationof
E482Guide for Application of Neutron Transport Methods
error estimates (covariance file), and documentation.Afurther
for Reactor Vessel Surveillance
requirementforcomponentsoftheASTM-recommendedcross
E560Practice for Extrapolating Reactor Vessel Surveillance
section file is their internal consistency when combined with
3
Dosimetry Results, E 706(IC) (Withdrawn 2009)
sensor measurements and used to determine a neutron spec-
E693Practice for Characterizing Neutron Exposures in Iron
trum.
and Low Alloy Steels in Terms of Displacements Per
1.3 Specifications for use include energy region of
Atom (DPA)
applicability, data processing requirements, and application of
E844Guide for Sensor Set Design and Irradiation for
uncertainties.
Reactor Surveillance
E853PracticeforAnalysisandInterpretationofLight-Water
1.4 This guide is directly related to and should be used
Reactor Surveillance Neutron Exposure Results
primarily in conjunction with Guides E482 and E944, and
E854Test Method for Application and Analysis of Solid
Practices E560, E185, and E693.
State Track Recorder (SSTR) Monitors for Reactor Sur-
1.5 TheASTM cross section and uncertainty file represents
veillance
a generally available data set for use in sensor set analysis.
E910Test Method for Application and Analysis of Helium
However, the availability of this data set does not preclude the
Accumulation Fluence Monitors for Reactor Vessel Sur-
use of other validated data, either proprietary or nonpropri-
veillance
etary. When alternate cross section files that deviate from the
E944Guide for Application of Neutron Spectrum Adjust-
requirements laid out in this standard are used, the deviations
ment Methods in Reactor Surveillance
should be noted to the customer of the dosimetry application.
E1005Test Method for Application and Analysis of Radio-
1.6 This standard does not purport to address all of the
metric Monitors for Reactor Vessel Surveillance
safety concerns, if any, associated with its use. It is the
E2005Guide for Benchmark Testing of Reactor Dosimetry
responsibility of the user of this standard to establish appro-
in Standard and Reference Neutron Fields
priate safety, health, and environmental practices and deter-
mine the applicability of regulatory limitations prior to use.
3. Terminology
1.7 This international standard was developed in accor-
3.1 Definitions of Terms Specific to This Standard:
dance with internationally recognized principles on standard-
1 2
This guide is under the jurisdiction of ASTM Committee E10 on Nuclear For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Technology and Applications and is the direct responsibility of Subcommittee contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
E10.05 on Nuclear Radiation Metrology. Standards volume information, refer to the standard’s Document Summary page on
Current edition approved March 1, 2020. Published April 2020. Originally the ASTM website.
3
published as E1018–84. Last previous edition approved in 2013 as E1018– 09 The last approved version of this historical standard is referenced on
ɛ1
(2013) . DOI: 10.1520/E1018-20. www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
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E1018 − 20
3.1.1 benchmark field—a limited number of neutron fields 3
...
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.
´1
Designation: E1018 − 09 (Reapproved 2013) E1018 − 20
Standard Guide for
1
Application of ASTM Evaluated Cross Section Data File
This standard is issued under the fixed designation E1018; 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
ε NOTE—The title of this guide and the Referenced Documents were updated in May 2017.
1. Scope
1.1 This guide covers the establishment and use of an ASTM evaluated nuclear data cross section and uncertainty file for
analysis of single or multiple sensor measurements in neutron fields related to light water reactor LWR-Pressure Vessel
Surveillance (PVS). These fields include in- and ex-vessel surveillance positions in operating power reactors, benchmark fields,
and reactor test regions.
1.2 Requirements for establishment of ASTM-approvedASTM-recommended cross section files address data format, evaluation
requirements, validation in benchmark fields, evaluation of error estimates (covariance file), and documentation. A further
requirement for components of the ASTM-approvedASTM-recommended cross section file is their internal consistency when
combined with sensor measurements and used to determine a neutron spectrum.
1.3 Specifications for use include energy region of applicability, data processing requirements, and application of uncertainties.
1.4 This guide is directly related to and should be used primarily in conjunction with Guides E482 and E944, and Practices
E560, E185, and E693.
1.5 The ASTM cross section and uncertainty file represents a generally available data set for use in sensor set analysis. However,
the availability of this data set does not preclude the use of other validated data, either proprietary or nonproprietary. When
alternate cross section files are used that deviate from the requirements laid out in this standard, standard are used, the deviations
should be noted to the customer ofrof the dosimetry application.
1.6 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.
1.7 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
E185 Practice for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance
3
E560 Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results, E 706(IC) (Withdrawn 2009)
E693 Practice for Characterizing Neutron Exposures in Iron and Low Alloy Steels in Terms of Displacements Per Atom (DPA)
E844 Guide for Sensor Set Design and Irradiation for Reactor SurveiillanceSurveillance
E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Neutron Exposure Results
E854 Test Method for Application and Analysis of Solid State Track Recorder (SSTR) Monitors for Reactor Surveillance
E910 Test Method for Application and Analysis of Helium Accumulation Fluence Monitors for Reactor Vessel Surveillance
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 June 1, 2013March 1, 2020. Published July 2013April 2020. Originally published as E1018 – 84. Last previous edition approved in 20092013
ɛ1
as E1018-09. – 09 (2013) . DOI: 10.1520/E1018-09R13E01.10.1520/E1018-20.
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
The last approved version of this historical standard is referenced on www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Dr
...
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