ASTM E1018-09
(Guide)Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
SIGNIFICANCE AND USE
The ENDF/B library in the United States and similar libraries elsewhere, such as JEF (9), JENDL (7), and BROND (8), provide a compilation of neutron cross section and other nuclear data for use by the nuclear community. The availability of these excellent and consistent 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 ENDF/B Dosimetry File (5, 10), consisting of activation cross sections important for dosimetry applications. This file was made available worldwide. Later, other“ Special Purpose” files were introduced (23). In the ENDF/B-VI compilation (41), dosimetry files were identified, but they no longer appeared as separate evaluation files. The ENDF/V-VII compilation (37) removed most of the 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 is 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.
Another file of evaluated neutron cross section data has been established by the International Atomic Energy Agency (IAEA) for reactor dosimetry applications. This file, the International Reactor Dosimetry File (IRDF-2002) (6), draws upon the ENDF/B files and supplements these evaluations with a set of reactions evaluated by groups often outside of the United States. Some of the IRDF-2002 supplemental reactions represent material evaluations that are currently being examined by the CSEWG. The supplemental IRDF-2002 evaluations only include the specific reactions of interest to the dosimetry community and not a full material evaluation. The ENDF community requires a complete evaluati...
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-approved 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-approved 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, the deviations should be noted to the customer ofr 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 and health practices and determine the applicability of regulatory limitations prior to use.
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Designation: E1018 − 09
StandardGuide for
Application of ASTM Evaluated Cross Section Data File,
1
Matrix E706 (IIB)
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 2. Referenced Documents
2
1.1 This guide covers the establishment and use of an 2.1 ASTM Standards:
ASTMevaluatednucleardatacrosssectionanduncertaintyfile E170Terminology Relating to Radiation Measurements and
for analysis of single or multiple sensor measurements in Dosimetry
neutron fields related to light water reactor LWR-Pressure E185Practice for Design of Surveillance Programs for
Vessel Surveillance (PVS). These fields include in- and ex- Light-Water Moderated Nuclear Power Reactor Vessels
vessel surveillance positions in operating power reactors, E482Guide for Application of Neutron Transport Methods
benchmark fields, and reactor test regions. for Reactor Vessel Surveillance, E706 (IID)
E560Practice for Extrapolating Reactor Vessel Surveillance
1.2 Requirements for establishment of ASTM-approved
3
Dosimetry Results, E 706(IC) (Withdrawn 2009)
cross section files address data format, evaluation
E693Practice for Characterizing Neutron Exposures in Iron
requirements, validation in benchmark fields, evaluation of
and Low Alloy Steels in Terms of Displacements Per
error estimates (covariance file), and documentation.Afurther
Atom (DPA), E 706(ID)
requirement for components of the ASTM-approved cross
E706MasterMatrixforLight-WaterReactorPressureVessel
section file is their internal consistency when combined with
3
Surveillance Standards, E 706(0) (Withdrawn 2011)
sensor measurements and used to determine a neutron spec-
E844Guide for Sensor Set Design and Irradiation for
trum.
Reactor Surveillance, E 706 (IIC)
1.3 Specifications for use include energy region of
E853PracticeforAnalysisandInterpretationofLight-Water
applicability, data processing requirements, and application of
Reactor Surveillance Results, E706(IA)
uncertainties.
E854Test Method for Application and Analysis of Solid
State Track Recorder (SSTR) Monitors for Reactor
1.4 This guide is directly related to and should be used
primarily in conjunction with Guides E482 and E944, and Surveillance, E706(IIIB)
E910Test Method for Application and Analysis of Helium
Practices E560, E185, and E693.
Accumulation Fluence Monitors for Reactor Vessel
1.5 TheASTM cross section and uncertainty file represents
Surveillance, E706 (IIIC)
a generally available data set for use in sensor set analysis.
E944Guide for Application of Neutron Spectrum Adjust-
However, the availability of this data set does not preclude the
ment Methods in Reactor Surveillance, E 706 (IIA)
use of other validated data, either proprietary or nonpropri-
E1005Test Method for Application and Analysis of Radio-
etary. When alternate cross section files are used that deviate
metric Monitors for Reactor Vessel Surveillance, E 706
from the requirements laid out in this standard, the deviations
(IIIA)
should be noted to the customer ofr the dosimetry application.
E2005Guide for Benchmark Testing of Reactor Dosimetry
1.6 This standard does not purport to address all of the
in Standard and Reference Neutron Fields
safety concerns, if any, associated with its use. It is the
responsibility of the user of this standard to establish appro-
3. Terminology
priate safety and health practices and determine the applica-
3.1 Definitions of Terms Specific to This Standard:
bility of regulatory limitations prior to use.
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 Applicationsand 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 June 1, 2009. Published December 2009. Originally the ASTM website.
3
publishedasE1018–84.Lastpreviouseditionapprovedin2001asE1018-01.DOI: The last approved version of this historical standard is referenced on
10.1520/E1018-09. 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 − 09
3.1.1 benchmark field—a limited number of neutron fields 3.1.1.3 controlled environment—these environments are
have been identified as benchmark fields for the purpose of well-defined neutron fields with some spectral definiti
...
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 1018–95 Designation:E1018–09
Standard Guide for
Application of ASTM Evaluated Cross Section Data File,
1
Matrix E 706E 706E706 (IIB)
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 (ϵ) indicates an editorial change since the last revision or reapproval.
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 r
elatedrelatedtolightwaterreactorLWR-PressureVesselSurveillance(PVS).Thesefieldsincludein-andex-vesselsurveillance
positions in operating power reactors, benchmark fields, and reactor test regions.
1.2 Requirements for establishment of ASTM-approved 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 theASTM-approved 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.
1.4This guide is directly related to and should be used primarily in conjunction with Guides E 482 and E 944E 482E 944, and
Practices E 560, E 185, and E 693E 560E 185E 693
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.
1.5TheASTM 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.
1.5 TheASTMcrosssectionanduncertaintyfilerepresentsagenerallyavailabledatasetforuseinsensorsetanalysis.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, the deviations should be noted
to the customer ofr 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 and health practices and determine the applicability of regulatory
limitations prior to use.
2. Referenced Documents
2
2.1 ASTM Standards:
E170 Terminology Relating to Radiation Measurements and Dosimetry
,
E185 Practice for Conducting Surveillance Tests for Light Water-Cooled Nuclear Power Reactor Vessels, E706 (IF) Practice
for Design of Surveillance Programs for Light-Water Moderated Nuclear Power Reactor Vessels
3
E482 Guide for Application of Neutron Transport Methods for Reactor Vessel Surveillance, E706 (IID),
2,3
E560 Practice for Extrapolating Reactor Vessel Surveillance Dosimetry Results, E706 (IC) E 706(IC)
E693 Practice for Characterizing Neutron Exposures in Iron and LowAlloy Steels inTerms of Displacements PerAtom (DPA),
2,3
E706 (ID) E 706(ID)
,
2 3
E706 Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706 (O) E 706(0)
,
2 3
E844844 Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E706 (IIC) E 706 (IIC)
2,3
E853 Practice for Analysis and Interpretation of Light-Water Reactor Surveillance Results, E706 (IA) E706(IA)
1
This guide is under the jurisdiction of ASTM Committee E-10 E10 on Nuclear Technology and Applications and is the direct responsibility of Subcommittee E10.05
on Nuclear Radiation Metrology.
Current edition approved April 15, 1995. Published June 1995. Originally published as E 1018–84. Last previous edition E 1018–84(1991).
Current edition approved June 1, 2009. Published December 2009. Originally published as E1018 – 84. Last previous edition approved in 2001 as E1018-01. DOI:
10.1520/E1018-09.
2
The reference in parentheses refers to Section 5 as well as Figs. 1 and 2 of Matrix E 706E 706.
2
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM 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.
Copyri
...
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