BUGLE-96: A Revised Multigroup Cross Section Library for LWR Applications Based on ENDF/B-VI Release 3
Conference
·
OSTI ID:226082
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
A revised multigroup cross-section library based ON ENDF/B-VI Release 3 has been produced for light water reactor shielding and reactor pressure vessel dosimetry applications. This new broad-group library, which is designated BUGLE-96, represents an improvement over the BUGLE-93 library released in February 1994 and is expected to replace the BUGLE-93 data. The cross-section processing methodology is the same as that used for producing BUGLE-93 and is consistent with ANSI/ANS 6.1.2. As an added feature, cross-section sets having upscatter data for four thermal neutron groups are included in the BUGLE-96 package available from the Radiation Shielding Information Center. The upscattering data should improve the application of this library to the calculation of more accurate thermal fluences, although more computer time will be required. The incorporation of feedback from users has resulted in a data library that addresses a wider spectrum of user needs.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AC05-96OR22464
- OSTI ID:
- 226082
- Report Number(s):
- CONF-960415--37; ON: DE96009870
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
97 MATHEMATICS AND COMPUTING
BIOLOGICAL SHIELDING
BWR TYPE REACTORS
CROSS SECTIONS
Data Library
GAMMA RADIATION
Light Water Reactor Shielding
MULTIGROUP THEORY
NEUTRON REACTIONS
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
PWR TYPE REACTORS
RADIATION TRANSPORT
Reactor Pressure Vessel Dosimetry Applications
VERIFICATION
97 MATHEMATICS AND COMPUTING
BIOLOGICAL SHIELDING
BWR TYPE REACTORS
CROSS SECTIONS
Data Library
GAMMA RADIATION
Light Water Reactor Shielding
MULTIGROUP THEORY
NEUTRON REACTIONS
NUCLEAR DATA COLLECTIONS
Nuclear Criticality Safety Program (NCSP)
PWR TYPE REACTORS
RADIATION TRANSPORT
Reactor Pressure Vessel Dosimetry Applications
VERIFICATION