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Production and Testing of the Vitamin-B6 Fine-Group and the BUGLE-93 Broad-Group Neutron/Photon Cross-Section Libraries Derived from ENDF/B-VI Nuclear Data

Ingersoll, DT
section Head and research staff,Nuclear Analysis and Shielding SectionOak Ridge National Laboratory,TN,

White, JE
Research staff,Engineering Physics Information Center (EPIC)Oak Ridge National Laboratory,TN,

Wright, RQ
Research staff,Oak Ridge National Laboratory,TN,

Hunter, HT
section Head and research staff,Nuclear Analysis and Shielding SectionOak Ridge National Laboratory,TN,

Slater, CO
section Head and research staff,Nuclear Analysis and Shielding SectionOak Ridge National Laboratory,TN,

MacFarlane, RE
Research staff,Los Alamos National Laboratory,NM,

Greene, NM
Research staff,Oak Ridge National Laboratory,TN,

Pages: 10    Published: Jan 1994

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Source: STP1228-EB

Abstract

A new multigroup cross-section library based on ENDF/B-VI data has been produced and tested for light water reactor shielding and reactor pressure vessel dosimetry applications. The broad-group library is designated BUGLE-93. The processing methodology is consistent with ANSI/ANS 6.1.2, since the ENDF data were first processed into a fine-group, “pseudo problem-independent” format and then collapsed into the final broad-group format. The fine-group library is designated VITAMIN-B6. An extensive integral data testing effort was also performed. In general, results using the new data show significant improvements relative to earlier ENDF data.

Keywords:
Nuclear data, cross sections, pressure vessel dosimetry, reactor shielding

Paper ID: STP15161S
Committee/Subcommittee: E10.01
DOI: 10.1520/STP15161S
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