Thermal neutron streaming effects and WIMS analysis of the Penn State subcritical graphite pile
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:552414
- Pennsylvania State Univ., University Park, PA (United States)
This analysis was performed on the Pennsylvania State University (PSU) subcritical reactor to find more accurate values for such nuclear parameters as the thermal fuel utilization factor, thermal diffusion length in the graphite, migration area, k{sub eff}, etc. The analysis involved using the Winfrith Integrated Multigroup Scheme (WIMS) code as well as various hand calculations to find and compare those parameters. The data found in this analysis will be used by future students in the Penn State laboratory courses.
- OSTI ID:
- 552414
- Report Number(s):
- CONF-971125-; ISSN 0003-018X; TRN: 98:001625
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 77; Conference: 1997 American Nuclear Society (ANS) winter meeting, Albuquerque, NM (United States), 16-20 Nov 1997; Other Information: PBD: 1997
- Country of Publication:
- United States
- Language:
- English
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