A comparison of the BUGLE-80, SAILOR, and ELXSIR neutron cross-section libraries for PWR pressure vessels surveillance dosimetry and shielding applications
Journal Article
·
· Nuclear Technology; (United States)
OSTI ID:6989365
- Pennsylvania State Univ., University Park, PA (United States)
- MPM Research and Consulting, State College, PA (United States)
In this paper three multigroup neutron cross-section libraries are used in synthesized three-dimensional discrete ordinates transport analyses to investigate their similarities, differences, and results for pressurized water reactor (PWR) pressure vessel surveillance dosimetry and shielding applications. The calculated-to-experimental (C/E) rations and the calculated reaction rates of several fast reactions are compared for the BUGLE-80, SAILOR, and ELXSIR cross-section libraries at the 97-deg surveillance capsule of the San Onofre Nuclear Generation Station Unit 2 (SONGS-2) and at the 90- and 97-deg (C/E ratios only) cavity dosimetry locations for another PWR (referred to as Reactor X).
- OSTI ID:
- 6989365
- Journal Information:
- Nuclear Technology; (United States), Journal Name: Nuclear Technology; (United States) Vol. 100:1; ISSN 0029-5450; ISSN NUTYBB
- Country of Publication:
- United States
- Language:
- English
Similar Records
Flux and fluence determination using the material scrapings approach
Evaluation of anisotropy effects in pressure vessel fluence calculations using the BUGLE-93 library
Transport analysis of several cross-section libraries used for reactor pressure vessel fluence calculations
Conference
·
Tue Dec 31 23:00:00 EST 1991
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:7145471
Evaluation of anisotropy effects in pressure vessel fluence calculations using the BUGLE-93 library
Journal Article
·
Fri Dec 30 23:00:00 EST 1994
· Transactions of the American Nuclear Society
·
OSTI ID:91997
Transport analysis of several cross-section libraries used for reactor pressure vessel fluence calculations
Journal Article
·
Sun Jan 31 23:00:00 EST 1993
· Nuclear Technology; (United States)
·
OSTI ID:6757333
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99 GENERAL AND MISCELLANEOUS
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BARYONS
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CONTAINERS
CROSS SECTIONS
DOSIMETRY
ELEMENTARY PARTICLES
EMISSION
ENERGY RANGE
ENRICHED URANIUM REACTORS
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FERMIONS
HADRONS
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NATIONAL ORGANIZATIONS
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REACTORS
REGULATIONS
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WATER MODERATED REACTORS