ANSI ANS 19.1-2002 nuclear data sets for reactor design calculations《反应堆设计计算用核数据集》.pdf

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1、ANSI/ANS-19.1-2002nuclear data sets forreactor design calculationsANSI/ANS-19.1-2002REAFFIRMED June 17, 2011 ANSI/ANS-19.1-2002 (R2011) This standard has been reviewed and reaffirmed with the recognition that it may reference other standards and documents that may have been superseded or withdrawn.

2、The requirements of this document will be met by using the version of the standards and documents referenced herein. It is the responsibility of the user to review each of the references and to determine whether the use of the original references or more recent versions is appropriate for the facili

3、ty. Variations from the standards and documents referenced in this standard should be evaluated and documented. This standard does not necessarily reflect recent industry initiatives for risk informed decision-making or a graded approach to quality assurance. Users should consider the use of these i

4、ndustry initiatives in the application of this standard. ANSI/ANS-19.1-2002American National StandardNuclear Data Sets forReactor Design CalculationsSecretariatAmerican Nuclear SocietyPrepared by theAmerican Nuclear SocietyStandards CommitteeWorking Group ANS-19.1Published by theAmerican Nuclear Soc

5、iety555 North Kensington AvenueLa Grange Park, Illinois 60526 USAApproved July 23, 2002by theAmerican National Standards Institute, Inc.AmericanNationalStandardDesignation of this document as an American National Standard attests thatthe principles of openness and due process have been followed in t

6、he approvalprocedure and that a consensus of those directly and materially affected bythe standard has been achieved.This standard was developed under procedures of the Standards Committee ofthe American Nuclear Society; these procedures are accredited by the Amer-ican National Standards Institute,

7、Inc., as meeting the criteria for AmericanNational Standards. The consensus committee that approved the standardwas balanced to ensure that competent, concerned, and varied interests havehad an opportunity to participate.An American National Standard is intended to aid industry, consumers, gov-ernme

8、ntal agencies, and general interest groups. Its use is entirely voluntary.The existence of an American National Standard, in and of itself, does notpreclude anyone from manufacturing, marketing, purchasing, or using prod-ucts, processes, or procedures not conforming to the standard.By publication of

9、 this standard, the American Nuclear Society does not insureanyone utilizing the standard against liability allegedly arising from or afterits use. The content of this standard reflects acceptable practice at the time ofits approval and publication. Changes, if any, occurring through developmentsin

10、the state of the art, may be considered at the time that the standard issubjected to periodic review. It may be reaffirmed, revised, or withdrawn atany time in accordance with established procedures. Users of this standardare cautioned to determine the validity of copies in their possession and toes

11、tablish that they are of the latest issue.The American Nuclear Society accepts no responsibility for interpretations ofthis standard made by any individual or by any ad hoc group of individuals.Requests for interpretation should be sent to the Standards Department atSociety Headquarters. Action will

12、 be taken to provide appropriate response inaccordance with established procedures that ensure consensus on theinterpretation.Comments on this standard are encouraged and should be sent to SocietyHeadquarters.Published byAmerican Nuclear Society555 North Kensington AvenueLa Grange Park, Illinois 605

13、26 USACopyright 2004 by American Nuclear Society. All rights reserved.Any part of this standard may be quoted. Credit lines should read “Extracted fromAmerican National Standard ANSI0ANS-19.1-2002 with permission of the publisher,the American Nuclear Society.” Reproduction prohibited under copyright

14、 conventionunless written permission is granted by the American Nuclear Society.Printed in the United States of AmericaForewordThis Foreword is not a part of American National Standard Nuclear Data Sets forReactor Design Calculations, ANSI0ANS-19.1-2002.!It is the intent of this American National St

15、andard to present specifications forthe preparation of nuclear data sets for use in reactor physics computer pro-grams employed in the design of nuclear reactors and to specify certain data setsas standards. The nuclear data used in reactor design calculations are funda-mental physical quantities an

16、d, hence, are independent of reactor type. The lackof complete, exact experimental measurements requires the use of evaluatedestimates of the data. This standard specifies guidelines for such evaluationsand specifies how the resulting data sets should be processed, tested, validated,and documented.T

17、his standard is intended primarily for nuclear data used for reactor core cal-culations. However, it may be of use in shielding calculations and in other areas,such as dosimetry and fusion.This standard presents specifications for the preparation of evaluated nucleardata sets, processed continuous d

18、ata sets, and energy averaged data sets for usein nuclear reactors. ENDF0B-VI is identified as a standard evaluated data set.An MCNP cross-section library is identified as a standard processed continuousdata set. It is believed that the development of standard averaged data sets foruse in reactor de

19、sign is an achievable goal, and therefore, procedures have beenestablished in this standard for achieving this objective.This standard was developed by Working Group ANS-19.l of the American Nu-clear Society Standards Committee, which had the following member at the timeit prepared and approved this

20、 standard for revision:D. R. Harris, Chairman, Rensselaer Polytechnic InstituteStandards Subcommittee ANS-19 of the American Nuclear Society had the fol-lowing members at the time it processed and approved this revised standard:D. Cokinos, ChairmanS. BakerR. D. CacciapoutiA. L. CasadeiR. T. ChiangD.

21、 J. DiamondD. R. HarrisJ. KatakuraL. LoisR. D. MostellerL. D. NobleR. T. PerryC. T. RomboughR. B. RothrockR. B. RoubenA. WeitzbergW. B. WilsonThis standard was processed and approved for submittal to ANSI by the N17,Research Reactors, Reactor Physics, Radiation Shielding, and ComputationalMethods Co

22、mmittee on ANSI0ANS-19.1, Nuclear Data Sets for Reactor DesignCalculations. Committee approval of the standard does not necessarily implythat all committee members voted for its approval. At the time it approved thisstandard, the N17 Committee had the following members:iR. E. Carter, IndividualD. Co

23、kinos, Brookhaven National LaboratoryB. Dodd, Health Physics Society/International Atomic Energy AgencyD. Duffey, University of MarylandW. A. Holt, American Public Health AssociationWilliam C. Hopkins, Bechtel CorporationL. I. Kopp, IndividualT. Marsh, U.S. Nuclear Regulatory CommissionJ. Miller, In

24、stitute of Electrical and Electronics Engineers/Gamma-MetricsJ. E. Olhoeft, IndividualT. M. Raby, National Institute of Standards and TechnologyW. J. Richards, University of California, DavisT. Schmidt, Sandia National LaboratoriesR. Seale, University of ArizonaA. O. Smetana, Savannah River National

25、 LaboratoryJ. F. Torrence, National Institute of Standards and TechnologyE. G. Tourigny, U.S. Department of EnergyD. K. Trubey, IndividualA. Weitzberg, Scientech, Inc.W. L. Whittemore, GA Technologies, Inc.iiContentsSection Page1 Scope . 11.1 General 11.2 Applications 12 Definitions 13 Evaluated Dat

26、a Sets . 23.1 General 23.2 Data Sources . 23.3 Preparation 33.4 Estimation of Accuracy . 43.5 Qualification . 43.6 Testing 53.7 Documentation . 54 Processed Continuous Data Sets 54.1 General 54.2 Sources 64.3 Preparation 64.4 Checking 64.5 Qualification . 64.6 Documentation . 75 Averaged Data Sets 7

27、5.1 General 75.2 Sources 75.3 Preparation 75.4 Checking 85.5 Qualification . 85.6 Documentation . 96 Data Sets Meeting the Specifications of This Standard . 96.1 General 96.2 Standard Evaluated Data Sets 96.3 Standard Processed Continuous Data Sets . 96.4 Standard Averaged Data Sets . 97 References

28、10AppendixAppendix . 11FigureFigure 1 Schematic representation of scope 2 iii Nuclear Data Sets for ReactorDesign Calculations1. Scope1.1 GeneralThis standard identifies and describes the spec-ifications for developing, preparing, and docu-menting nuclear data sets to be used in reactordesign calcul

29、ations. The specifications includea! criteria for acceptance of evaluated nu-clear data sets; b! criteria for processing eval-uated data and preparation of processedcontinuous data and averaged data sets; andc! identification of specific evaluated, pro-cessed continuous, and averaged data sets thatm

30、eet these criteria for specific reactor types.1.2 ApplicationsNuclear data sets shall consist of basicmicro-scopic nuclear physics data that include butare not limited to the important neutron-induced reactions. The data set, in the pro-cessed form, will be primarily utilized as inputto fission reac

31、tor core design calculations butmay have applications to other fields, such asshielding, dosimetry, or fusion studies.The specific types of data sets considered tofall within the scope of this standard are showninFigure 1 and defined more precisely in Sec-tion 2, “Definitions.” As indicated inFigure

32、 1,the scope of this standard does not pertaintoexperimental techniques for the measurementof nuclear data or to the development of nu-clear model theory. The scope does not apply toa few-group collapsed data set, which is repre-sentative of a particular application except fora requirement for the d

33、ocumentation of col-lapsed data sets when such data sets are pre-pared as part of the testing of the nuclear datasets covered by this standard.The distinguished features of data sets consid-ered to fall within the scope of this standardare that they can be represented as being ap-plicable to a wide

34、range of reactor composi-tions, geometries, and spectra.2 Definitionsbenchmark: A well-defined set of physical ex-periments or mathematical constructs whoseresults are judged to be sufficiently accurate tobe used as calculational reference points. Thejudgment is made by a group of experts in thesubj

35、ect area.CSEWG: Cross-Section Evaluation WorkingGroup, comprising representatives from orga-nizations participating in the cooperative ef-fort of developing the best possible evaluateddata setsee “The Evaluated Nuclear Data FileVersion VIENDF0B-VI!” 1#.1The CSEWG sec-retariat is the National Nuclear

36、 Data Centerat Brookhaven National Laboratory.data set: A collection of microscopic cross sec-tions and nuclear constants encompassing therange of materials and reaction processes neededfor the application area of interest.evaluated data set: A data set that is com-pletely and uniquely specified ove

37、r the rangesof energy and angles important to reactor cal-culations. Such a data set isajudgment basedon information available experimental mea-surement results and nuclear theories! as tothe best physical description of the interactionprocesses. An evaluated data set is intended tobe independent of

38、 specific reactor composi-tions, geometries, energy group structures, orspectra.processed continuous data set: A data setprepared by expansion or compaction of an eval-uated data set using specified algorithms. Sucha data set is intended to be independent ofspecific reactor compositions, geometries,

39、 en-ergy group structures, or spectra.averaged data set: A data set prepared byaveraging an evaluated data set or a processedcontinuous data set with a specified weightingfunction over a specified detailed energy group1Numbers in brackets refer to corresponding numbers in Section 7, “References.”1st

40、ructure. The group structure and weightingfunction are selected so that the averaged dataset is applicable to a wide range of reactoranalyses, e.g.,light water reactors. Application-dependent, collapsed data sets are dealt within American National Standard “Determina-tion of Steady State Neutron Rea

41、ction RateDistributions and Reactivity of Nuclear Reac-tors,” ANSI0ANS-19.3-1995 2#.standard data set: A standard data evalu-ated, processed continuous, or averaged! set isone that meets the specifications set forth inthis standard.ENDF/B: An evaluated nuclear data file devel-oped by CSEWG, prepared

42、 according to a spec-ified format, for use in a computer-orientedsystem that creates, stores, and retrieves eval-uated data sets.ENDF/B-n: The nth CSEWG-approved ver-sion of the ENDF0B series of evaluated datasets.processing code: A computer program de-signed to generate continuous, averaged, multi-

43、group, or few-group data sets from evaluateddata sets. Similarly, processing codes can bedesigned to generate averaged, multigroup, orfew-group data sets from processed continuousdata sets.3 Evaluated data sets3.1 GeneralEvaluated data sets shall be represented byspecifying unique piecewise continuo

44、us valuesgiven as a function of incident particle energy,secondary particle energy, secondary particleangle, or by parameters for a precisely definedanalytical function.The evaluated data sets shall be derived frombasic experimental data, data calculated fromnuclear models, and data deduced from nu-

45、clear systematics, as well as consideration ofintegral measurements. The evaluated datashould be specified for an incident neutron en-ergy range from 0.0001 eV up to 20 MeV andshall be in at least the detail required for pro-cessed and averaged data sets. The evaluateddata set should containanestima

46、te of the un-certainty of data contained therein by means ofa covariance file.3.2 Data sources3.2.1 Experimental microscopic dataThe following subsections list the data sourcescommonly used for evaluation of microscopicdata. All data sources considered in the evalu-ation shall be documented.Figure 1

47、 Schematic representation of scopeAmerican National Standard ANSI0ANS-19.1-200223.2.1.1 Nuclear reaction dataThe National Nuclear Data Center at Brook-haven National Laboratory maintains a com-pilation of measured nuclear reaction data.These data should serve as a major source ofexperimental nuclear

48、 reaction data for use inpreparing the evaluated data.3.2.1.2 Neutron cross-section dataThe National Nuclear Data Center at Brook-haven National Laboratory maintains a compi-lation of measured cross-section data. Thesedata should serve as a major source of experi-mental cross data for use in prepari

49、ng the eval-uated data.3.2.1.3 Other nuclear dataThe National Nuclear Data Center maintains acompilation of nuclear structure data that areuseful in preparing evaluated decay data. TheNational Nuclear Data Center also maintainsreferences for charged-particle cross-section datathat may serve as a source of such data asa,n! cross sections3.2.2 Nuclear model codesPreparation of certain evaluated data requiresuse of nuclear model codes to fit and extrapo-late from measured data. The use of these nu-clear model codes shall be documented to permitthorough review by parties ski