1、Designation: E1018 09 (Reapproved 2013)1Standard Guide forApplication of ASTM Evaluated Cross Section Data File1This standard is issued under the fixed designation E1018; the number immediately following the designation indicates the year oforiginal adoption or, in the case of revision, the year of
2、last revision. A number in parentheses indicates the year of last reapproval. Asuperscript epsilon () indicates an editorial change since the last revision or reapproval.1NOTEThe title of this guide and the Referenced Documents were updated in May 2017.1. Scope1.1 This guide covers the establishment
3、 and use of anASTM evaluated nuclear data cross section and uncertainty filefor analysis of single or multiple sensor measurements inneutron fields related to light water reactor LWR-PressureVessel Surveillance (PVS). These fields include in- and ex-vessel surveillance positions in operating power r
4、eactors,benchmark fields, and reactor test regions.1.2 Requirements for establishment of ASTM-approvedcross section files address data format, evaluationrequirements, validation in benchmark fields, evaluation oferror estimates (covariance file), and documentation. A furtherrequirement for component
5、s of the ASTM-approved crosssection file is their internal consistency when combined withsensor measurements and used to determine a neutron spec-trum.1.3 Specifications for use include energy region ofapplicability, data processing requirements, and application ofuncertainties.1.4 This guide is dir
6、ectly related to and should be usedprimarily in conjunction with Guides E482 and E944, andPractices E560, E185, and E693.1.5 The ASTM cross section and uncertainty file representsa generally available data set for use in sensor set analysis.However, the availability of this data set does not preclud
7、e theuse of other validated data, either proprietary or nonpropri-etary. When alternate cross section files are used that deviatefrom the requirements laid out in this standard, the deviationsshould be noted to the customer ofr the dosimetry application.1.6 This standard does not purport to address
8、all of thesafety concerns, if any, associated with its use. It is theresponsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use.1.7 This international standard was developed in accor-dance
9、with internationally recognized principles on standard-ization established in the Decision on Principles for theDevelopment of International Standards, Guides and Recom-mendations issued by the World Trade Organization TechnicalBarriers to Trade (TBT) Committee.2. Referenced Documents2.1 ASTM Standa
10、rds:2E170 Terminology Relating to Radiation Measurements andDosimetryE185 Practice for Design of Surveillance Programs forLight-Water Moderated Nuclear Power Reactor VesselsE482 Guide for Application of Neutron Transport Methodsfor Reactor Vessel SurveillanceE560 Practice for Extrapolating Reactor V
11、essel SurveillanceDosimetry Results, E 706(IC) (Withdrawn 2009)3E693 Practice for Characterizing Neutron Exposures in Ironand Low Alloy Steels in Terms of Displacements PerAtomE844 Guide for Sensor Set Design and Irradiation forReactor SurveiillanceE853 Practice forAnalysis and Interpretation of Lig
12、ht-WaterReactor Surveillance ResultsE854 Test Method for Application and Analysis of SolidState Track Recorder (SSTR) Monitors for Reactor Sur-veillanceE910 Test Method for Application and Analysis of HeliumAccumulation Fluence Monitors for Reactor Vessel Sur-veillanceE944 Guide for Application of N
13、eutron Spectrum Adjust-ment Methods in Reactor SurveillanceE1005 Test Method for Application and Analysis of Radio-metric Monitors for Reactor Vessel SurveillanceE2005 Guide for Benchmark Testing of Reactor Dosimetryin Standard and Reference Neutron Fields1This guide is under the jurisdiction of AST
14、M Committee E10 on NuclearTechnology and Applicationsand is the direct responsibility of SubcommitteeE10.05 on Nuclear Radiation Metrology.Current edition approved June 1, 2013. Published July 2013. Originallypublished as E1018 84. Last previous edition approved in 2009 as E1018-09. DOI:10.1520/E101
15、8-09R13E01.2For referenced ASTM standards, visit the ASTM website, www.astm.org, orcontact ASTM Customer Service at serviceastm.org. For Annual Book of ASTMStandards volume information, refer to the standards Document Summary page onthe ASTM website.3The last approved version of this historical stan
16、dard is referenced onwww.astm.org.Copyright ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United StatesThis international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Prin
17、ciples for theDevelopment of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.13. Terminology3.1 Definitions of Terms Specific to This Standard:3.1.1 benchmark fielda limited number of neutron fieldshave been ident
18、ified as benchmark fields for the purpose ofdosimetry sensor calibration and dosimetry cross section datadevelopment and testing (1, 2).4See Terminology E170. Thesefields are permanent facilities in which experiments can berepeated. In addition, differential neutron spectrum measure-ments have been
19、performed in many of the fields to provide,together with transport calculations and integral measurements,the best state-of-the-art neutron spectrum evaluation. Tosupplement the data available from benchmark fields, most ofwhich are limited in fluence rate intensity, reactor test regionsfor dosimetr
20、y method validation have also been defined,including both in-reactor and ex-vessel dosimetry positions.Table 1 lists some of the neutron fields that have been used fordata development, testing, and evaluation. Other benchmarkfields used for testing LWR calculations are described inE2005.3.1.1.1 stan
21、dard fieldthese fields are produced by facili-ties and apparatus that are stable, permanent, and whose fieldsare reproducible with neutron fluence rate intensity, energyspectra, and angular fluence rate distributions characterized tostate-of-the-art accuracy. Important standard field quantitiesmust
22、be verified by interlaboratory measurements. These fieldsexist at the National Institute of Standards and Technology(NIST) and other laboratories.3.1.1.2 reference fieldthese fields are produced by facili-ties and apparatus that are permanent and whose fields arereproducible, less well characterized
23、 than a standard field, butacceptable as a measurement reference by the community ofusers.3.1.1.3 controlled environmentthese environments arewell-defined neutron fields with some spectral definitions,employed for a restricted set of validation experiments over arange of energies.3.1.2 dosimetry cro
24、ss sectionscross sections used for do-simetry application and which provide the total cross sectionfor production of particular (measurable) reaction products.These include fission cross sections for production of fissionproducts, activation cross sections for the production of radio-active nuclei,
25、and cross sections for production of measurablestable products, such as helium.3.1.3 evaluated datavalues of physical quantities repre-senting a current best estimate. Such estimates are developedby experts considering measurements or calculations of thequantity of interest, or both. Cross section e
26、valuations, forexample, are conducted by teams of scientists such as theENDF/B Cross Section Evaluation Working Group (CSEWG)(see also section 3.1.5.2).3.1.4 Evaluated Nuclear Data File (ENDF)consists ofneutron cross sections and other nuclear data evaluated fromavailable experimental measurements a
27、nd calculations. Twotypes of ENDF files exist.3.1.4.1 ENDF/B filesevaluated files officially approved byCSEWG see ENDF documents 102 (15), 201 (16), and 216(17) after suitable review and testing.3.1.4.2 ENDF/A filesevaluated files including outdatedversions of ENDF/B, the International Reactor Dosim
28、etry File(IRDF-2002) (18), the Japanese Evaluated Nuclear Data Li-brary (JENDL) (19), BROND (USSR) (20) and other evaluatedcross section libraries. These files include partial as well ascomplete evaluations.3.1.5 integral data/differential dataintegral data are datapoints that represent an integrate
29、d sensors response over arange of energy. Examples are measurements of reaction ratesor fission rates in a fission neutron spectrum. Differential data4The boldfaced numbers in parentheses refer to the list of references at the endof this guide.TABLE 1 Partial List of Neutron Fields for Validating Do
30、simetry Cross SectionsNeutron FieldSample FacilityLocationEnergyUseful Energy Rangefor Data TestingAReferenceDocumentationMedian AverageStandard FieldsThermal Maxwellian NIST . . 0.51 eV252Cf Fission NIST (3) 1.68 MeV 2.13 MeV 100 keV8 MeV Ref 3Designation XCF-5-N1235U Thermal Fission NIST (3) 1.57
31、MeV 1.97 MeV 250 keV3 MeV Ref 3Mol-25(4, 5) Designation XU5-5-N1ISNF NIST (6) 0.56 MeV ;1.0 MeV 10 keV3.5 MeV Ref 3NISUS (7) Designation ISNF(5)-1-L1Mol- (8)Reference FieldsBIG TEN LANL (9, 10) 0.33 MeV 0.58 MeV 10 keV3 MeV Ref 9Fast Reactor Benchmark20CFRMF EGG-Idaho (9, 11) 0.375 MeV 0.76 MeV 4 ke
32、V2.5 MeV Ref 9Dosimetry Benchmark 1Controlled EnvironmentsPCA-PV ORNL (12) . . 100 keV10 MeV Ref 12EBR-II ANL-West (13) . . 1 keV10 MeV Ref 13FFTF HEDL (14) . . 1 keV10 MeV Ref 14AThe requirements for the data testing energy range are much more strict for reference and standard fields than for contr
33、olled fields. These testing energy ranges reflectcomparison with calculations based on published spectra for reference and standard fields, but only address data reproducibility for controlled environments.E1018 09 (2013)12are measurements at single energy points or over a relativelysmall energy ran
34、ge. Examples are time-of-flight measurements,proton recoil spectrometry, etc. (21).3.1.6 uncertainty filethe uncertainty in cross section datahas been included with evaluated cross section libraries that areused for dosimetry applications. Because of the correlationsbetween the data points or cross
35、section parameters, theseuncertainties, in general, cannot be expressed as variances, butrather a covariance matrix must be specified. Through the useof the covariance matrix, uncertainties in derived quantities,such as average cross sections, can be calculated more accu-rately.4. Significance and U
36、se4.1 The ENDF/B library in the United States and similarlibraries elsewhere, such as JEF (22), JENDL (19), andBROND (20), provide a compilation of neutron cross sectionand other nuclear data for use by the nuclear community. Theavailability of these excellent and consistent evaluations makespossibl
37、e standardized usage, thereby allowing easy referencingand intercomparisons of calculations. However, as the firstENDF/B files were developed it became apparent that theywere not adequate for all applications. This need resulted in thedevelopment of the ENDF/B Dosimetry File (17, 23), consist-ing of
38、 activation cross sections important for dosimetry appli-cations. This file was made available worldwide. Later, other“Special Purpose” files were introduced (24). In the ENDF/B-VIcompilation (25), dosimetry files were identified, but they nolonger appeared as separate evaluation files. The ENDF/V-V
39、IIcompilation (26) removed most of the covariance files used bythe dosimetry community. It kept the covariance files for the“standard cross sections” in a special sub-library, but thecovariance data in this sub-library is only provided over theenergy range in which each reaction is considered to be
40、a“standard”, and does not include the full energy range requiredfor LWR PVS dosimetry applications.4.2 Another file of evaluated neutron cross section data hasbeen established by the International Atomic Energy Agency(IAEA) for reactor dosimetry applications. This file, theInternational Reactor Dosi
41、metry File (IRDF-2002) (18), drawsupon the ENDF/B files and supplements these evaluations witha set of reactions evaluated by groups often outside of theUnited States. Some of the IRDF-2002 supplemental reactionsrepresent material evaluations that are currently being exam-ined by the CSEWG. The supp
42、lemental IRDF-2002 evalua-tions only include the specific reactions of interest to thedosimetry community and not a full material evaluation. TheENDF community requires a complete evaluation beforeincluding it in the main ENDF/B evaluated library.4.3 The application to LWR surveillance dosimetry may
43、introduce new data needs that can best be satisfied by thecreation of a dedicated cross section file. This file shall be in aform designed for easy application by users (minimal process-ing).The file shall consist of the following types of informationor indicate the sources of the following type of
44、data that shouldbe used to supplement the file contents:4.3.1 Dosimetry cross sections for fission, activation, he-lium production sensor reactions in LWR environments insupport of radiometric, solid state track recorder, heliumaccumulation dosimetry methods (see Test Methods E853,E854, E910, and E1
45、005).4.3.2 Other cross sections or sensor response functionsuseful for active or passive dosimetry measurements, forexample, the use of neutron absorption cross sections torepresent attenuation corrections due to covers or self-shielding.4.3.3 Cross sections for damage evaluation, such as dis-placem
46、ents per atom (dpa) in iron.4.3.4 Related nuclear data needed for dosimetry, such asbranching ratios, fission yields, and atomic abundances.4.4 The ASTM-recommended cross sections and uncertain-ties are based mostly on the ENDF/B-VI and IRDF-2002dosimetry files. Damage cross sections for materials s
47、uch asiron have been added in order to promote standardization ofreported dpa measurements within the dosimetry community.Integral measurements from benchmark fields and reactor testregions shall be used to ensure self-consistency and establishcorrelations between cross sections. The total file is i
48、ntended tobe as self-consistent as possible with respect to both differentialand integral measurements as applied in LWR environments.This self-consistency of the data file is mandatory for LWR-pressure vessel surveillance applications, where only verylimited dosimetry data are available.Where modif
49、ications to anexisting evaluated cross section have been made to obtain thisself-consistence in LWR environments, the modifications shallbe detailed in the associated documentation (see 5.6).5. Establishment of Cross Section File5.1 CommitteeThe cross section and uncertainty file shallbe established and maintained under a responsible task groupappointed by Subcommittee E10.05 on Nuclear RadiationMetrology. The task group shall review, and approve all databefore insertion of the file and ensure the adequate testing hasbeen performed on the file contents.
