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Department of Hot Laboratories
JAERI-Review 2005-003, 105 Pages, 2005/02
JAERI-Review-2005-003.pdf:21.21MB
no abstracts in English
Sekiya, Yukou*; Takaki, Naoyuki*; Tonoike, Kotaro
no journal, ,
Fuel pellets may be scattered, in the accident of Fukushima Daiichi Nuclear Power Station, without melting in the containment vessels. Precise information of composition of the burnt BWR fuel assemblies is necessary to study the criticality control method for the scattered fuel pellets. In this study, distribution of residual 
U enrichment was evaluated, for each of the reactors, using a model of a fuel-rod array in a fuel assembly.
Kojima, Kensuke; Okumura, Keisuke
no journal, ,
The MOSRA system has been developing to improve the applicability of the neutronic characteristic analyses. The cell calculation module MOSRA-SRAC is a core module of MOSRA, and applicability tests for realistic problems are required. As a test, we joined the benchmark "Burnup Credit Criticality Benchmark Phase IIIC". The benchmark requested the neutronic characteristics for a BWR fuel assembly with gadolinium, which had been used in the TEPCO's Fukushima Daiichi Nuclear Power Station. Because of a restriction of MOSRA-SRAC, the geometry was partially homogenized. To verify the module's applicability including the homogenization effects, the multiplication factor and the nuclide compositions were compared with the well-validated code MVP-BURN. As the results, the applicability of MSORA-SRAC for the assembly was verified. Additionally, it was also shown that the homogenization effects were smaller than the difference due to the calculation methods.
Sekiya, Yukou*; Takaki, Naoyuki*; Tonoike, Kotaro
no journal, ,
no abstracts in English