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ENDF/B-VIII.0: The 8 th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data

  • Author(s): Brown, DA
  • Chadwick, MB
  • Capote, R
  • Kahler, AC
  • Trkov, A
  • Herman, MW
  • Sonzogni, AA
  • Danon, Y
  • Carlson, AD
  • Dunn, M
  • Smith, DL
  • Hale, GM
  • Arbanas, G
  • Arcilla, R
  • Bates, CR
  • Beck, B
  • Becker, B
  • Brown, F
  • Casperson, RJ
  • Conlin, J
  • Cullen, DE
  • Descalle, M-A
  • Firestone, R
  • Gaines, T
  • Guber, KH
  • Hawari, AI
  • Holmes, J
  • Johnson, TD
  • Kawano, T
  • Kiedrowski, BC
  • Koning, AJ
  • Kopecky, S
  • Leal, L
  • Lestone, JP
  • Lubitz, C
  • Márquez Damián, JI
  • Mattoon, CM
  • McCutchan, EA
  • Mughabghab, S
  • Navratil, P
  • Neudecker, D
  • Nobre, GPA
  • Noguere, G
  • Paris, M
  • Pigni, MT
  • Plompen, AJ
  • Pritychenko, B
  • Pronyaev, VG
  • Roubtsov, D
  • Rochman, D
  • Romano, P
  • Schillebeeckx, P
  • Simakov, S
  • Sin, M
  • Sirakov, I
  • Sleaford, B
  • Sobes, V
  • Soukhovitskii, ES
  • Stetcu, I
  • Talou, P
  • Thompson, I
  • van der Marck, S
  • Welser-Sherrill, L
  • Wiarda, D
  • White, M
  • Wormald, JL
  • Wright, RQ
  • Zerkle, M
  • Žerovnik, G
  • Zhu, Y
  • et al.
Abstract

© 2018 We describe the new ENDF/B-VIII.0 evaluated nuclear reaction data library. ENDF/B-VIII.0 fully incorporates the new IAEA standards, includes improved thermal neutron scattering data and uses new evaluated data from the CIELO project for neutron reactions on 1H, 16O, 56Fe, 235U, 238U and 239Pu described in companion papers in the present issue of Nuclear Data Sheets. The evaluations benefit from recent experimental data obtained in the U.S. and Europe, and improvements in theory and simulation. Notable advances include updated evaluated data for light nuclei, structural materials, actinides, fission energy release, prompt fission neutron and γ-ray spectra, thermal neutron scattering data, and charged-particle reactions. Integral validation testing is shown for a wide range of criticality, reaction rate, and neutron transmission benchmarks. In general, integral validation performance of the library is improved relative to the previous ENDF/B-VII.1 library.

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