Results of MCNP calculations for criticality safety benchmarks with ENDF/B-V and ENDF/B-VI libraries

Journal Article · Sat Dec 30 23:00:00 EST 1995 · Transactions of the American Nuclear Society

OSTI ID:186578

Iverson, J L; Mosteller, R D ^[1]

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1. Los Alamos National Lab., NM (United States)

This paper summarizes results obtained using the ENDF/B-V library and the ENDF/B-VI with the MCNP code, for a series of 26 benchmark experiments. These calculations represent the first extensive benchmarking of ENDF/B-VI cross sections libraries against measured data from benchmark critical experiments.

• OSTI ID: 186578
• Report Number(s): CONF-950601--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 72; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

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