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- W112583693 abstract "It is common practice in ENDF/B (Evaluated Nuclear Data File) to represent neutron cross sections in the unresolved resonance region by specifying the average values and distribution laws of resonance parameters. This formalism allows the calculation of resonance self-shielding and of its variation with temperature. The purpose of this paper is to present a test of the validity of the formalism by comparing self-shielding factors computed with the ENDF/B unresolved formalism with values computed with the resolved resonance parameters recently evaluated for the neutron cross sections of {sup 235}U." @default.
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- W112583693 date "1989-11-01" @default.
- W112583693 modified "2023-09-24" @default.
- W112583693 title "Test of the ENDF/B (Evaluated Nuclear Data File) unresolved resonance formalism for sup 235 U" @default.
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