Analysis of Mixed Oxide Fuel Critical Experiments EPICURE and MISTRAL with Nuclear Analysis Code for BWR

• Published in: Nihon Genshiryoku Gakkai wabun ronbunshi = Transactions of the Atomic Energy Society of Japan Vol. 5; no. 1; pp. 34 - 44
• Main Authors: ISHII, Kazuya, FUSHIMI, Atsushi, HINO, Tetsushi, MARUYAMA, Hiromi, IZUTSU, Sadayuki, SASAGAWA, Masaru, IWATA, Yutaka
• Format: Journal Article
• Language: Japanese
• Published: Atomic Energy Society of Japan 2006
• Subjects: BWR type reactors; critical experiment; EPICURE; experimental analysis; MISTRAL; MOX; nuclear analysis code; nuclear characteristic
• ISSN: 1347-2879; 2186-2931
• DOI: 10.3327/taesj2002.5.34

For the purpose of verification of the nuclear analysis method of BWR for mixed oxide (MOX) cores, UO2 and MOX fuel critical experiments EPICURE and MISTRAL were analyzed using nuclear design codes HINES and CERES with ENDF/B nuclear data file. The critical keffs of the absorber worth experiments, the water hole worth experiments and the 2D void worth experiments agreed with those of the reference experiments within about 0.1%Δk. The root mean square differences of radial power distributions between calculation and measurement were almost less than 2.0%. The calculated reactivity worth values of the absorbers, the water hole and the 2D void agreed with the measured values within nearly experimental uncertainties. These results indicate that the nuclear analysis method of BWR in the present paper give the same accuracy for the UO2 cores and the MOX cores.