Nuclear Engineering and Technology

  • 제37권1호
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  • Pages.11-24
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  • 2005
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지

STATUS AND PERSPECTIVE OF NUCLEAR DATA PRODUCTION, EVALUATION AND VALIDATION

  • TRKOV A. (International Atomic Energy Agency, Nuclear Data Section)
  • 발행 : 2005.02.01
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초록

A very important feature in the development of nuclear technology has been and will continue to be the flow of information from nuclear data production to the various applications fields in nuclear technology. Both, nuclear data and this communications flow are defined in this paper. Nuclear data result from specific technical activities including their production, evaluation, processing, verification, validation and applications. These activities are described, focusing on nuclear reactor calculations. Mathematical definitions of different types of nuclear data are introduced, and international forums involved in nuclear data activities are listed. Electronic links to various sources of information available on the web are specified, whenever possible.

키워드

참고문헌

  1. NEA Nuclear Science Committee: International Handbook of Evaluated Criticality Safety Benchmark Experiments, (ICSBEP), NEA/NSC/ DOC(95)(03), September 2004 Edition
  2. OECD Nuclear Energy Agency, Idaho National Engineering and Environmental Laboratory and Argonne National Laboratory: International Reactor Physics Experiment Project (IRPhEP), 3 December 2004
  3. OECD Nuclear Energy Agency and Radiation Safety Information Computational Center: SINBAD -an International Database for Integral Shielding Experiments, OECD/NEA Data Bank, 15 December 2004, Package ID NEA1552, 1553, 1517, http://www.nea.fr/html/dbprog/cpsabsabc.html
  4. O. Bersillon, L.R. Greenwood, P.J. Griffin, W. Mannhart, P.K. McLaughlin, H.J. Nolthenius, R. Paviotti-Corcuera, A. Trkov, K.I. Zolotarev, E.M. Zsolnay: International Reactor Dosimetry File-2002 (IRDF-2002), IAEA-TECDOC, to be published
  5. S.F. Mughabghab: Thermal Neutron Capture Cross Sections, Resonance Integrals and g-Factors, International Atomic Energy Agency, IAEA(NDS)-440, February 2003, http://www-nds.iaea.org/indc_sel.html
  6. INW-RUG/KFKI: User's Manual KAYZERO/ SOLCOI Version 5a Software Package, DSM Research, Geleen (2003)
  7. L. . Perrot, A. Billebaud, R. Brissot, A. Giorni, D. Heuer, J.-M. Loiseaux, O. Meplan, J.-B. Viano: Precise Validation of Database (n, ${\gamma}$) Cross Sections Using a Lead-Slowing-Down Spectrometer and Simulation from 0.1 eV to 30 keV: Methodology and Data for a Few Elements, 144, 2 (2003), pp.142-156
  8. H.D. Lemmel: Short Guide to EXFOR, IAEA-NDS-1 Rev.7, November 1996
  9. IAEA: WRENDA 93/94 World Request List for Nuclear Data, International Atomic Energy Agency, INDC(SEC)-104
  10. J.K. Dickens (Ed.): Nuclear Data for Science and Technology, International conference, Gatlinburg, 9-13 May 1994, ANS (1994)
  11. A.J. Koning, S. Hilaire, M.C. Duijvestijn : TALYS: Comprehensive nuclear reaction modelling, Proceedings of the International Conference on Nuclear Data for Science and Technology-ND2004, Sep. 26-Oct. 1, 2004, Santa Fe, USA, to be published
  12. Argonne National Laboratory West: GMA: Generalized Least-Squares Evaluation of Related Cross Sections for ENDF/B Based on Gauss, Markov, and Aitken, RSICC Code Package PSR-367, Radiation Safety Information Computational Center (RSICC), http://www-rsicc.ornl.gov/rsicc.html
  13. Oak Ridge National Laboratory: GLUCS: A Generalized Least-Squares Code System for Updating Cross Section Evaluations with Correlated Data Sets, RSICC Code Package PSR-192, Radiation Safety Information Computational Center (RSICC), http://www-rsicc.ornl.gov/rsicc.html
  14. D.W. Muir: ZOTT99, NEA Package ID IAEA1371/01, NEA Data Bank, http://www.nea.fr/html/dbprog/
  15. D. C. Dodder, G. M. Hale, and K. Witte : Energy Dependent Analysis Code for Nuclear Reactions, Los Alamos National Laboratory (unpublished)
  16. Chen Zhenpeng: RAC R-Matrix Code, Physics Department, Tsinghua University, Beijing, PRC (unpublished)
  17. N.M. Larson: SAMMY-M6: Code System for Multilevel R-Matrix Fits to Neutron and Charged-Particle Cross-Section Data Using Bayes' Equations, RSICC Code Package PSR- 158, Radiation Safety Information Computational Center (RSICC), http://www-rsicc.ornl.gov /rsicc.html
  18. M.C. Moxon: REFIT, A Least Square Fitting Program for Resonance Analysis of Neutron Transmission and Capture Data, AEA-InTec-0630, CBNM/ST/90-131-1 (August 1991), NEA Package ID NEA0914, http://www.nea.fr/html/dbprog/cpsabsabc.html
  19. O. Schwerer: UKNDL-80 Contents and Documentation, IAEA-NDS-30, 1980
  20. H.D. Lemmel: KEDAK-4 the Karlsruhe Evaluated Neutron Data Library-Summary of Contents and Format}, IAEA-NDS-21, Rev.4, 1986
  21. D. Garber, C. Dunford, S. Pearlstein (Eds.): Data Formats and Procedures for the Evaluated Nuclear Data File, ENDF, BNL-NCS-50496 (ENDF-102), BrookhavenNational Laboratory, New York, 1975
  22. R. Kinsey (Ed.1979), B.A. Magurno (Rev.1983): Data Formats and Procedures for the Evaluated Neutron Data File ENDF/B-V, BNL-NCS-50496 (ENDF-102),Brookhaven National Laboratory, New York, 1983
  23. V. McLane, C.L. Dunford, P.F. Rose: Data formats and procedures for the evaluated nuclear data file ENDF-6, Rev. 6, April 2001
  24. O. Schwerer, H.D. Lemmel: Index of Nuclear Data Libraries Available from the IAEA Nuclear Data Section, IAEA-NDS-7, 2002/7, July 2002, http://www-nds.iaea.org/reports/nds-7.pdf
  25. A. I. Blokhin, et al., Current Status of Russian Nuclear Data Libraries, Nuclear Data For Science and Technology, Volume 2, p. 695, edited by J. K. Dickens (American Nuclear Society, LaGrange Park, IL, 1994)
  26. Liang Qi-Chang et.al. (H.D. Lemmel Ed.): CENDL-2, Chinese Evaluated Nuclear Data Library}, (Updated and supplemented in 1995), IAEA-NDS-61 Rev.3, Nov.1996
  27. D. Garber (Ed.) : ENDF/B Summary Documentation, BNL-17541 (ENDF-201), Brookhaven National Laboratory, New York, 1975
  28. R. Kinsey (Ed.1979) : ENDF/B Summary Documentation}, BNL-NCS-17541 (ENDF-102) 3rd Ed., Brookhaven National Laboratory, New York, 1979
  29. Cross Section Evaluation Working Group, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991), edited by P.F. Rose, National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY, USA
  30. C. Nordborg, M. Salvatores, Status of the JEF Evaluated Data Library, Nuclear Data for Science and Technology, edited by J. K. Dickens (American Nuclear Society, LaGrange, IL, 1994)
  31. H. Gruppelaar: EFF-2, the European Fusion File, Summary documentation IAEA-NDS-170, 1995
  32. The JEFF-3.0 General Purpose Library, JEFF Report 19, to be published
  33. T. Nakagawa, et al., Japanese Evaluated Nuclear Data Library, Version 3, Revision 2, J. Nucl. Sci. Technol. 32, 1259 (1995) https://doi.org/10.3327/jnst.32.1259
  34. JAERI Nuclear Data Center: 'Japanese Evaluated Nuclear Data Library, Version 3, Revision 3 (JENDL-3.3)', private communication (2002)
  35. C.L. Dunford: ENDF Utility Codes Release 7.0, Brookhaven National Laboratory, October 26, 2004, private communication, http://www.nndc.bnl.gov/nndcscr/endf/index.html
  36. D.E. Cullen, PREPRO 2002 - ENDF/B Pre-processing Codes, IAEA-NDS-39 Rev. 11, Feb. 5, 2003, http://www-nds.iaea.org/ndspub/endf/prepro/
  37. A. Trkov: ENDVER - The ENDF File Verification Support Package, IAEA-NDS-77 Rev. 0, August 2001
  38. R.E. MacFarlane, D.W. Muir: NJOY99.0: Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B Data, RSICC Code Package PSR-480
  39. N. M. Greene, W. E. Ford, III, L. M. Petrie and J. W. Arwood: AMPX-77: Modular Code System for Generating Coupled Multigroup Neutron-Gamma Libraries from ENDF/B, RSICC Code Package PSR-315
  40. A. Trkov, M. Ravnik: CORD-2 Package for PWR Nuclear Core Design Calculations, Proceedings of the International Conference on Reactor Physics and reactor computations, Tel-Aviv, Israel, 23-26 Jan. 1994. (Eds.: Ygal Ronen, Ezra Elias), Ben-Gurion University of Negev Press (1994)., NEA Package ID-IAEA1226/03, 23 May 1996, http://www.nea.fr/html/dbprog/
  41. J.R. Askew, F.J. Fayers, P.B. Kemshell: A General Description of the Lattice Code WIMS, J.Brit.Nucl.Eng. Soc. 5, October 1966, Package ID-NEA1507/04, 25 February 2004, http://www.nea.fr/html/dbprog/
  42. A. Trkov, M. Ravnik: Effective Diffusion Homogenization of Cross Sections for Pressurized Water Reactor Core Calculations, Nucl.Sci.Enging. 116, 2, pp.86-95, (1994)
  43. R. Goldstein, E.R. Cohen: Theory of Resonance Absorption of Neutrons, Nucl.Sci.Eng. 13, pp.132-140, (1962)
  44. G. Forti: Evaluation of Resonance Integrals in Homogeneous and Heterogeneous Systems - an Intermediate Approximation, Nucl.Sci.Eng. 19, pp.449-457, (1964)
  45. J.J. Duderstadt, L.J. Hamilton: Nuclear Reactor Analysis, John Wiley & Sons, Inc. (1976)