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
Conference
·
OSTI ID:10104046
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
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.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Nuclear Regulatory Commission (USNRC)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 10104046
- Report Number(s):
- CONF-930809--13; ON: DE94002438
- Country of Publication:
- United States
- Language:
- English
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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
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Production and Testing of the VITAMIN-B7 Fine-Group and BUGLE-B7 Broad-Group Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data
Technical Report
·
Sat Dec 31 19:00:00 EST 1994
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OSTI ID:10108149
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
Technical Report
·
Thu Apr 19 00:00:00 EDT 2001
·
OSTI ID:779795
Production and Testing of the VITAMIN-B7 Fine-Group and BUGLE-B7 Broad-Group Coupled Neutron/Gamma Cross-Section Libraries Derived from ENDF/B-VII.0 Nuclear Data
Technical Report
·
Fri Sep 30 00:00:00 EDT 2011
·
OSTI ID:1411183
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100
220200
97 MATHEMATICS AND COMPUTING
CALIFORNIUM 252
COMPONENTS AND ACCESSORIES
CROSS SECTIONS
DOSIMETRY
IRON
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
Nuclear data
PRESSURE VESSELS
RADIATION EFFECTS
SHIELDING
THEORY AND CALCULATION
WATER COOLED REACTORS
cross sections
pressure vessel dosimetry
reactor shielding
220100
220200
97 MATHEMATICS AND COMPUTING
CALIFORNIUM 252
COMPONENTS AND ACCESSORIES
CROSS SECTIONS
DOSIMETRY
IRON
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
Nuclear data
PRESSURE VESSELS
RADIATION EFFECTS
SHIELDING
THEORY AND CALCULATION
WATER COOLED REACTORS
cross sections
pressure vessel dosimetry
reactor shielding