Published 1995
| Version v1
Book
Automatic rapid processing cross-section libraries for the prediction of PWR spent fuel isotopic compositions
Description
Point-depletion calculations in the SCALE code system are performed with the ORIGEN-S code with problem-dependent cross-section libraries generated in the SAS2H sequence. This paper describes a methodology for cross-section generation for point-depletion calculations with the ORIGEN-S code which, in turn, serve as an alternative for the SCALE/SAS2H cross-section sequence. The adequacy of the methodology is evaluated by comparing measured and computed spent fuel isotopic compositions
Additional details
Publishing Information
- Publisher
- American Nuclear Society, Inc.
- Imprint Place
- La Grange Park, IL (United States)
- Imprint Title
- Proceedings of the international conference on mathematics and computations, reactor physics, and environmental analyses. Volume 1 and 2
- Imprint Pagination
- 1629 p.
- Journal Page Range
- p. 52-62.
Conference
- Title
- International conference on mathematics and computations, reactor physics, and environmental analyses.
- Dates
- 30 Apr - 4 May 1995.
- Place
- Portland, OR (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 28045639
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CROSS SECTIONS; ISOTOPE RATIO; O CODES; PWR TYPE REACTORS; S CODES; SPENT FUELS
- Descriptors DEC
- COMPUTER CODES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400
- Secondary number(s)
- CONF-950420--.