Verification of the CASMO-4 transport method based on BWR high-burnup 9 x 9 fuel critical experiments
- Toden Software Inc., Tokyo (Japan)
- Tokyo Electric Power Company, Tokyo (Japan)
Fuel designs for boiling water reactors (BWRs) have become far more heterogeneous owing to the high-burnup design and the improvements in the thermal hydraulics. The current generation of BWR fuel designs may contain complicated geometries; for instance, GE-11-type fuel design contains several partial length rods and a large island of water in the center of the 9 x 9 assembly. The characteristics method that has been introduced to CASMO-4 as a new transport method is expected to offer very accurate solutions of the neutron flux distributions for heterogeneous geometries. Although some numerical tests for BWR lattices, containing the 9 x 9 lattice, were performed against Monte Carlo results and advantages of the new method have been indicated, the straightforward verification test of this method to the 9 x 9 lattice based on the critical experiments is desirable. This paper presents the CASMO-4 benchmarking results for pin powers against critical experiments using BWR 9 x 9 (A-type fuel).
- OSTI ID:
- 411755
- Report Number(s):
- CONF-951006--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 73; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
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