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ENDF/B-VIII.1: Thermal Neutron Scattering Sublibrary

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Nobre, G.;Capote, R.;Pigni, M.;Trkov, A.;Mattoon, C.;Neudecker, D.;Brown, D.;Chadwick, M.;Kahler, A.;Kleedtke, N.;Zerkle, M.;Hawari, A.;Chapman, C.;Fleming, N.;Wormald, J.;Ramić, K.;Danon, Y.;Gibson, N.;Brain, P.;Paris, M.;Hale, G.;Thompson, I.;Barry, D.;Stetcu, I.;Haeck, W.;Lovell, A.;Mumpower, M.;Potel, G.;Kravvaris, K.;Noguere, G.;McDonnell, J.;Carlson, A.;Dunn, M.;Kawano, T.;Wiarda, D.;Al-Qasir, I.;Arbanas, G.;Arcilla, R.;Beck, B.;Bernard, D.;Beyer, R.;Brown, J.;Cabellos, O.;Casperson, R.;Cheng, Y.;Chimanski, E.;Coles, R.;Cornock, M.;Cotchen, J.;Crozier, J.;Cullen, D.;Daskalakis, A.;Descalle, M.-A.;DiJulio, D.;Dimitriou, P.;Dreyfuss, A.;Durán, I.;Ferrer, R.;Gaines, T.;Gillette, V.;Gert, G.;Guber, K.;Haverkamp, J.;Herman, M.;Holmes, J.;Hursin, M.;Jisrawi, N.;Junghans, A.;Kelly, K.;Kim, H.;Kim, K.;Koning, A.;Koštál, M.;Laramee, B.;Lauer-Coles, A.;Leal, L.;Lee, H.;Lewis, A.;Malec, J.;Damián, J.;Marshall, W.;Mattera, A.;Muhrer, G.;Ney, A.;Ormand, W.;Parsons, D.;Percher, C.;Pritychenko, B.;Pronyaev, V.;Qteish, A.;Quaglioni, S.;Rapp, M.;Ressler, J.;Rising, M.;Rochman, D.;Romano, P.;Roubtsov, D.;Schnabel, G.;Schulc, M.;Siemers, G.;Sonzogni, A.;Talou, P.;Thompson, J.;Trumbull, T.;Marck, S.;Vorabbi, M.;Wemple, C.;Wendt, K.;White, M.;Wright, R.

Description

The thermal neutron scattering law (TSL) sublibrary aims to describe the interaction of incident neutrons at thermal or sub-thermal energies with different compound materials such fuels, moderators and special-purpose materials. In ENDF/B-VIII.1 there was a large number of new and updated TSL evaluations, including traditional moderators (light water, Beryllium metal, Beryllium Oxide, Calcium Hydride, plastics (Polystyrene and Lucite), graphite (reactor-grade and crystalline), anhydrous Hydrogen Fluoride, and heavy paraffinic oil); exotic moderators (Beryllium Carbide, Zirconium Hydride, Yttrium Hydride, Lithium-7 Hydride and Deuteride), FLiBe molten salt, structural materials and cladding (Silicon Carbide, Silicon Dioxide, Zirconium Carbide), fuels (Plutonium Dioxide, Uranium Carbide, Uranium metal, Uranium Nitride, Uranium Dioxide, Uranium Hydride), and special purpose materials. In ENDF/B-VIII.1 we also distribute alongside the evaluated files, a comma-separated file (CSV), named TSL_MAT_numbers.csv, which lists all evaluated files in the current release and their corresponding unique MAT number.

Citations (0)

Mentions (0)

Metrics

Dataset Index

0.1

FAIR Score

15%

Citations

0

Mentions

0

Metrics Over Time

Publication Details

DOI

10.11578/endf/2571028

Publisher

Brookhaven National Lab

Assigned Domain

Subfield

Materials Chemistry

Field

Materials Science

Domain

Physical Sciences

Confidence Score

73%

Source

Scholar Data Model

Keywords

73 NUCLEAR PHYSICS AND RADIATION PHYSICSnuclear datanuclear data librarynuclear reaction datanuclear reactionsnuclear physicsENDFENDF/Bnuclear evaluationsnuclear reaction evaluationsevaluated nuclear dataneutron-induced reactionsdeuteron-induced reactionsproton-induced reactionsphotonuclear reactionsnuclear decayfission yieldsthermal scattering lawthermal-neutron scattering lawnuclear reactorsnuclear applicationsnuclear isotope productionnuclear criticality safetyreactor depletionnuclear a

Normalization Factors

FT

50.00

CTw

1.00

MTw

1.00