ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology
Description
We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes. The new evaluations are based on both experimental data and nuclear reaction theory predictions. The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron … continued below
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PDF-file: 125 pages; size: 4.7 Mbytes
Creation Information
Chadwick, M. B.; Oblozinsky, P.; Herman, M.; Greene, N. M.; McKnight, R. D.; Smith, D. L. et al. October 2, 2006.
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Authors
- Chadwick, M. B.
- Oblozinsky, P.
- Herman, M.
- Greene, N. M.
- McKnight, R. D.
- Smith, D. L.
- Young, P. G.
- MacFarlane, R. E.
- Hale, G. M.
- Haight, R. C.
- Frankle, S.
- Kahler, A. C.
- Kawano, T.
- Little, R. C.
- Madland, D. G.
- Moller, P.
- Mosteller, R.
- Page, P.
- Talou, P.
- Trellue, H.
- White, M.
- Wilson, W. B.
- Arcilla, R.
- Dunford, C. L.
- Mughabghab, S. F.
- Pritychenko, B.
- Rochman, D.
- Sonzogni, A. A.
- Lubitz, C.
- Trumbull, T. H.
- Weinman, J.
- Brown, D.
- Cullen, D. E.
- Heinrichs, D.
- McNabb, D.
- Derrien, H.
- Dunn, M.
- Larson, N. M.
- Leal, L. C.
- Carlson, A. D.
- Block, R. C.
- Briggs, B.
- Cheng, E.
- Huria, H.
- Kozier, K.
- Courcelle, A.
- Pronyaev, V.
- der Marck, S.
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Lawrence Livermore National Laboratory
Publisher Info: Lawrence Livermore National Laboratory (LLNL), Livermore, CAPlace of Publication: Livermore, California
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Description
We describe the next generation general purpose Evaluated Nuclear Data File, ENDF/B-VII.0, of recommended nuclear data for advanced nuclear science and technology applications. The library, released by the U.S. Cross Section Evaluation Working Group (CSEWG) in December 2006, contains data primarily for reactions with incident neutrons, protons, and photons on almost 400 isotopes. The new evaluations are based on both experimental data and nuclear reaction theory predictions. The principal advances over the previous ENDF/B-VI library are the following: (1) New cross sections for U, Pu, Th, Np and Am actinide isotopes, with improved performance in integral validation criticality and neutron transmission benchmark tests; (2) More precise standard cross sections for neutron reactions on H, {sup 6}Li, {sup 10}B, Au and for {sup 235,238}U fission, developed by a collaboration with the IAEA and the OECD/NEA Working Party on Evaluation Cooperation (WPEC); (3) Improved thermal neutron scattering; (4) An extensive set of neutron cross sections on fission products developed through a WPEC collaboration; (5) A large suite of photonuclear reactions; (6) Extension of many neutron- and proton-induced reactions up to an energy of 150 MeV; (7) Many new light nucleus neutron and proton reactions; (8) Post-fission beta-delayed photon decay spectra; (9) New radioactive decay data; and (10) New methods developed to provide uncertainties and covariances, together with covariance evaluations for some sample cases. The paper provides an overview of this library, consisting of 14 sublibraries in the same, ENDF-6 format, as the earlier ENDF/B-VI library. We describe each of the 14 sublibraries, focusing on neutron reactions. Extensive validation, using radiation transport codes to simulate measured critical assemblies, show major improvements: (a) The long-standing underprediction of low enriched U thermal assemblies is removed; (b) The {sup 238}U, {sup 208}Pb, and {sup 9}Be reflector biases in fast systems are largely removed; (c) ENDF/B-VI.8 good agreement for simulations of highly enriched uranium assemblies is preserved; (d) The underprediction of fast criticality of {sup 233,235}U and {sup 239}Pu assemblies is removed; and (e) The intermediate spectrum critical assemblies are predicted more accurately. We anticipate that the new library will play an important role in nuclear technology applications, including transport simulations supporting national security, nonproliferation, advanced reactor and fuel cycle concepts, criticality safety, medicine, space applications, nuclear astrophysics, and nuclear physics facility design. The ENDF/B-VII.0 library is archived at the National Nuclear Data Center, BNL. The complete library, or any part of it, may be retrieved from www.nndc.bnl.gov.
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PDF-file: 125 pages; size: 4.7 Mbytes
Subjects
Keywords
- Actinide Nuclei
- Cross Sections
- Fission Products
- Fuel Cycle
- Highly Enriched Uranium
- National Security
- Neutron Reactions
- Nuclear Data Collections
- Nuclear Physics
- Nuclear Reactions
- Photonuclear Reactions
- Proliferation
- Proton Reactions
- Radiation Transport
- Thermal Neutrons
- Zero Power Reactors
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Source
- Journal Name: Nuclear Data Sheets, vol. 107, no. 12, November 12, 2006, pp. 2931-3060
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- Report No.: UCRL-JRNL-225066
- Grant Number: W-7405-ENG-48
- Digital Object Identifier: https://doi.org/10.1016/j.nds.2006.11.001
- Office of Scientific & Technical Information Report Number: 900147
- Archival Resource Key: ark:/67531/metadc888955
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- October 2, 2006
Added to The UNT Digital Library
- Sept. 22, 2016, 2:13 a.m.
Description Last Updated
- July 17, 2020, 1:26 p.m.
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Chadwick, M. B.; Oblozinsky, P.; Herman, M.; Greene, N. M.; McKnight, R. D.; Smith, D. L. et al. ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology, article, October 2, 2006; Livermore, California. (https://digital.library.unt.edu/ark:/67531/metadc888955/: accessed July 18, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.