Publication | Open Access
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
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226
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2018
Year
Integral Validation TestingEngineeringNuclear PhysicsNuclear DataReactor PhysicsThermal Scattering DataNuclear MaterialsHigh-energy Nuclear ReactionPhysicsNuclear TheoryNew Endf/b-viii.0Neutron SourceBenchmark ExperimentsThermal NeutronNuclear EngineeringExperimental Nuclear PhysicsNatural SciencesNew StandardsTh Major ReleaseNeutron Scattering
The paper introduces the ENDF/B‑VIII.0 evaluated nuclear reaction data library. ENDF/B‑VIII.0 incorporates updated IAEA standards, enhanced thermal neutron scattering data, and new CIELO‑project evaluations for key isotopes, drawing on recent experimental results and theoretical advances across light nuclei, structural materials, actinides, fission characteristics, and charged‑particle reactions. Validation tests across criticality, reaction‑rate, and neutron‑transmission benchmarks demonstrate that ENDF/B‑VIII.0 outperforms the previous ENDF/B‑VII.1 library.
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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