ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

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

doi:10.1016/j.nds.2006.11.001

ENDF/B-VII.0: Next Generation Evaluated Nuclear Data Library for Nuclear Science and Technology

Journal Article · Mon Oct 02 04:00:00 EDT 2006 · Nuclear Data Sheets, vol. 107, no. 12, November 12, 2006, pp. 2931-3060

DOI:https://doi.org/10.1016/j.nds.2006.11.001· OSTI ID:900147

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 more »

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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Research Organization:: Lawrence Livermore National Laboratory (LLNL), Livermore, CA

Sponsoring Organization:: USDOE

DOE Contract Number:: W-7405-ENG-48

OSTI ID:: 900147

Report Number(s):: UCRL-JRNL-225066

Journal Information:: Nuclear Data Sheets, vol. 107, no. 12, November 12, 2006, pp. 2931-3060, Journal Name: Nuclear Data Sheets, vol. 107, no. 12, November 12, 2006, pp. 2931-3060

Country of Publication:: United States

Language:: English

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R Matrix Analysis of the ²⁴¹ Pu Neutron Cross Sections in the Thermal to 300-eV Energy Range Derrien, H.; de Saussure, G. Nuclear Science and Engineering, Vol. 106, Issue 4 https://doi.org/10.13182/NSE90-A23767	journal	December 1990
Cross-Section Evaluations to 150 MeV for Accelerator-Driven Systems and Implementation in MCNPX Chadwick, M. B.; Young, P. G.; Chiba, S. Nuclear Science and Engineering, Vol. 131, Issue 3 https://doi.org/10.13182/NSE98-48	journal	March 1999
239Pu and 241Am (n, 2n) cross-section measurements near En = 14 MeV Lougheed, R. W.; Webster, W.; Namboodiri, M. N. Radiochimica Acta, Vol. 90, Issue 12 https://doi.org/10.1524/ract.2002.90.12_2002.833	journal	January 2002
Tables and graphs of atomic subshell and relaxation data derived from the LLNL Evaluated Atomic Data Library (EADL), Z = 1--100 Perkins, S. T.; Cullen, D. E.; Chen, M. H. https://doi.org/10.2172/10121422	report	October 1991
New thermal neutron scattering files for ENDF/B-VI release 2 MacFarlane, R. E. https://doi.org/10.2172/10192168	report	March 1994
Estimated (n,f) cross sections for 236,236m237,238-Np, 237,237m-Pu, and 240,241,242,242m,243,244,244m-Am isotopes Younes, W.; Becker, J.; Britt, H. https://doi.org/10.2172/15013937	report
Proposal for ENDF formats that describe emission of post-fission beta-delayed photons Brown, D.; Pruet, J.; Hedstrom, G. https://doi.org/10.2172/15014656	report	September 2004
Sensitivity and parametric evaluations of significant aspects of burnup credit for PWR spent fuel packages DeHart, M. D. https://doi.org/10.2172/254970	report	May 1996
New Monte Carlo simulations of the LLNL pulsed-sphere experiments Marchetti, A. A. https://doi.org/10.2172/304515	report	July 1998
GNASH: a preequilibrium, statistical nuclear-model code for calculation of cross sections and emission spectra. [In FORTRAN for CDC 7600] Young, P. G.; Arthur, E. D. https://doi.org/10.2172/5224192	report	November 1977
Tables and graphs of electron-interaction cross sections from 10 eV to 100 GeV derived from the LLNL Evaluated Electron Data Library (EEDL), Z = 1--100 Perkins, S. T.; Cullen, D. E.; Seltzer, S. M. https://doi.org/10.2172/5691165	report	November 1991
PRECO-D2: program for calculating preequilibrium and direct reaction double differential cross sections Kalbach, C. https://doi.org/10.2172/5772617	report	February 1985
Gamma rays, Q-values, and kerma factors Muir, D. W. https://doi.org/10.2172/7352303	report	February 1976
RCPO1 - A Monte Carlo program for solving neutron and photon transport problems in three dimensional geometry with detailed energy description and depletion capability Ondis, II, L. A.; Tyburski, L. J.; Moskowitz, B. S. https://doi.org/10.2172/755403	report	March 2000
Neutron cross section evaluations of fission products below the fast energy region Oh, S. Y.; Chang, J.; Mughabghab, S. https://doi.org/10.2172/759039	report	May 2000
Neutron total cross sections of 235u from transmission measurements in the energy range 2 kev to 300 kev and statistical model analysis of the data Derrien, H. https://doi.org/10.2172/815777	report	May 2000
Neutron Capture and Transmission Measurements and Resonance Parameter Analysis of Gadolinium Leinweber, G.; Barry, D. P.; Trbovich, M. J. https://doi.org/10.2172/859039	report	June 2005
Measurement of double-differential neutron emission spectra from uranium-238. Baba, Mamoru; Wakabayashi, Hidetaka; Ito, Nobuo Journal of Nuclear Science and Technology, Vol. 27, Issue 7 https://doi.org/10.3327/jnst.27.601	journal	January 1990
Re-evaluation of the Effective Delayed Neutron Fraction Measured by the Substitution Technique for a Light Water Moderated Low-enriched Uranium Core. Nakajima, Ken Journal of Nuclear Science and Technology, Vol. 38, Issue 12 https://doi.org/10.3327/jnst.38.1120	journal	January 2001
Adjustment of Total Delayed Neutron Yields of 235U, 238U and 239Pu in JENDL-3.2 Using Benchmark Experiments on Effective Delayed Neutron Fraction .BETA.eff. Sakurai, Takeshi; Okajima, Shigeaki Journal of Nuclear Science and Technology, Vol. 39, Issue 1 https://doi.org/10.3327/jnst.39.19	journal	January 2002
Reconsideration of the Theoretical Supplementation of Decay Data in Fission Product Decay Heat Summation Calculations Hagura, Naoto; Yoshida, Tadashi; Tachibana, Takahiro Journal of Nuclear Science and Technology, Vol. 43, Issue 5 https://doi.org/10.3327/jnst.43.497	journal	January 2006
Photonuclear Data - Abstract Sheets 1955 - 1982 Fuller, E. G.; Gerstenberg, Henry https://doi.org/10.6028/NBS.IR.83-2742v15	report	February 1986

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