The Outline and a draft report of the OECD/NEA burnup calculation benchmark "Phase-IIIC" for BWR 99 fuel assembly

Uchida, Yuriko; Suyama, Kenya; Kashima, Takao; Tonoike, Kotaro 

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.