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Suyama, Kenya; Uchida, Yuriko*; Kashima, Takao; Ito, Takuya*; Miyaji, Takamasa*
NEA/NSC/R(2015)6 (Internet), 253 Pages, 2016/03
The Expert Group on Burnup Credit Criticality Safety (EGBUC) of Working Party of Nuclear Criticality Safety (WPNCS) under the Nuclear Science Committee (NSC) of OECD/NEA has been assessing the accuracy of the burnup calculation code systems by organizing several international benchmarks. This Phase IIIC benchmark specification for BWR 9 by 9 type fuel assembly infinite two-dimensional model was proposed and approved in the meeting of the OECD/NEA/NSC/WPNCS Expert group on burnup credit criticality safety in September 2012 and distributed in October 2012 to the members of the WPNCS. We have set of thirty-five calculation results from sixteen institutes of nine countries. This report presents the results of the benchmark phase IIIC. By this benchmark results, we can confirm the certain progress of the burnup calculation capability than the time of Phase IIIB benchmark. The difference of the neutron multiplication factor generated by the difference of the burnup calculation results by the latest code systems is less than 3%.
-concrete systemIzawa, Kazuhiko; Uchida, Yuriko; Okubo, Kiyoshi; Totsuka, Masayoshi; Sono, Hiroki; Tonoike, Kotaro
Journal of Nuclear Science and Technology, 49(11), p.1043 - 1047, 2012/11
Times Cited Count：12 Percentile：66.54(Nuclear Science & Technology)Possibility of criticality of fuel debris in a form of UO-concrete mixture is evaluated by calculating infinite multiplication factor (
) for a study of criticality control on the fuel debris generated through the molten core concrete interaction (MCCI) in a severe accident of a light water reactor (LWR). The infinite multiplication factor can be greater than unity, which means that handling of the mixture is subject to criticality control. This paper shows that concrete have efficient slowing-down capability of neutron and points out the necessity of further investigations on the criticality of low-enriched UO-concrete system for actual handling of fuel debris.
Uchida, Yuriko; Suyama, Kenya; Kashima, Takao; Tonoike, Kotaro
no journal, ,
It is necessary to evaluate isotopic composition of spent fuel for the criticality safety evaluation of the fuel damaged in the Fukushima Daiichi NPS accident, which demands to evaluate uncertainty of the burnup calculation code system. Analysis with the latest nuclear data library and code was conducted on the burnup calculation benchmark "Phase-IIIB" established by OECD/NEA in late '90s to grasp difference between the new and old calculation results. This presentation shows the re-analysis result of the Phase-IIIB with the Integrated Burnup Code System SWAT3.1 which drives the continuous energy Monte Carlo code MVP and the combined point burnup calculation code ORIGEN2.
Kashima, Takao; Suyama, Kenya; Uchida, Yuriko; Tonoike, Kotaro; Takada, Tomoyuki*
no journal, ,
no abstracts in English
9 fuel assemblyUchida, Yuriko; Suyama, Kenya; Kashima, Takao; Tonoike, Kotaro
no journal, ,
It is necessary to evaluate the isotopic composition of the spent fuels for the criticality safety evaluation of the fuel damaged during the Fukushima Daiichi (1F) accident, which demands to evaluate the uncertainty of the burnup calculation code system. The Expert Group on Burnup Credit Criticality Safety of Working Party of Nuclear Criticality Safety under the NSC of OECD/NEA carried out the burnup calculation benchmark "Phase-IIIB" for BWR STEP-2 fuel, although it has been done more than 10 years ago. Because the latest BWR STEP-3 fuel were adopted in 1F and the calculation code and the nuclear data libraries have been revised, the Expert Group carries out the burnup calculation benchmark "Phase-IIIC" for BWR STEP-3 fuel since September 2012 by the proposal of JAEA. This presentation shows the outline and a draft report of this benchmark.
