Assessment of WIMS-AECL/RFSP for CANDU core analysis
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:411759
- Korea Atomic Energy Research Institute, Daejon (Korea, Democratic People`s Republic of)
The code system used for the design of, currently operating Canada deuterium uranium (CANDU) reactors consists of the cell code POWDERPUFS-V and the finite difference code RFSP. The use of POWDERPUFS-V is limited to natural uranium fuel because of the empirical correlations implemented. For the advanced CANDU fuel cycle using spent pressurized water reactor fuel in CANDU (DUPIC), it is necessary to adopt a lattice code that has a general application in isotopics and geometry modeling. For the DUPIC fuel cycle, it was decided to use WIMS-AECL and RFSP for the lattice parameter generation and core simulation, respectively, with the ENDF/B-V nuclear data processed for WIMS-AECL by Atomic Energy of Canada (AECL).
- OSTI ID:
- 411759
- Report Number(s):
- CONF-951006--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 73; ISSN TANSAO; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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