Validation of the Nuclear Design Method for MOX Fuel Loaded LWR Cores

Conference · Sun Jun 17 04:00:00 EDT 2001

OSTI ID:785203

Saji, E; Inoue, Y; Mori, M; Ushio, T

The actual batch loading of mixed-oxide (MOX) fuel in light water reactors (LWRs) is now ready to start in Japan. One of the efforts that have been devoted to realizing this batch loading has been validation of the nuclear design methods calculating the MOX-fuel-loaded LWR core characteristics. This paper summarizes the validation work for the applicability of the CASMO-4/SIMULATE-3 in-core fuel management code system to MOX-fuel-loaded LWR cores. This code system is widely used by a number of electric power companies for the core management of their commercial LWRs. The validation work was performed for both boiling water reactor (BWR) and pressurized water reactor (PWR) applications. Each validation consists of two parts: analyses of critical experiments and core tracking calculations of operating plants. For the critical experiments, we have chosen a series of experiments known as the VENUS International Program (VIP), which was performed at the SCK/CEN MOL laboratory in Belgium. VIP consists of both BWR and PWR fuel assembly configurations. As for the core tracking calculations, the operating data of MOX-fuel-loaded BWR and PWR cores in Europe have been utilized.

• Research Organization: Toden Software Inc., Tokyo (JP); Nuclear Engineering, Limited, Osaka (JP)
• Sponsoring Organization: None (US)
• OSTI ID: 785203
• Report Number(s): NONE; ISSN 0003-018X; CODEN TANSAO; ISSN 0003-018X; CODEN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
BATCH LOADING
BWR TYPE REACTORS
C CODES
COMPUTER-AIDED DESIGN
DESIGN
FUEL MANAGEMENT
JAPAN
MIXED OXIDE FUELS
PWR TYPE REACTORS
REACTOR CORES
S CODES
VALIDATION
WATER COOLED REACTORS