|Author||Terazu, Kuninobu ♦ Saji, Etsuro ♦ Arai, Shiro|
|Source||United States Department of Energy Office of Scientific and Technical Information|
|Subject Keyword||NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS ♦ BWR TYPE REACTORS ♦ FUEL ASSEMBLIES ♦ REACTOR LATTICES ♦ C CODES ♦ DESIGN ♦ BURNUP ♦ HYDRAULICS ♦ NEUTRON FLUX ♦ BENCHMARKS|
|Abstract||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).|
|Learning Resource Type||Article|
|Publisher Place||United States|
|Journal||Transactions of the American Nuclear Society|
|Technical Publication No.||CONF-951006-|
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