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Report No.
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Analysis of VENUS-2 MOX core measurements with a Monte Carlo code MVP

Nagaya, Yasunobu; Okumura, Keisuke; Mori, Takamasa

We have analyzed the VENUS-2 MOX core benchmark exercises by using a continuous-energy Monte Carlo code MVP with the nuclear data set JENDL-3.2 and ENDF/B-VI release 5. The VENUS-2 core is cruciform and consists of three fuel regions; the squared central region, the inner and the outer part of the peripheral region are fueled with 3.3% UO$$_2$$, 4.0% UO$$_2$$ and MOX. We have constructed 3-D quarter-symmetric calculation model as precisely as possible. All calculations were performed for 200 million histories including 1 million histories of 50 cycles for the initial guess. The C/E values of keff are 1.00500, 0.99793 for JENDL-3.2 and ENDF/B-VI, respectively. They are in good agreement with the experimental one. However, the JENDL-3.2 result overestimates slightly by about 0.5%. For the pin power distribution, the systematic overestimation can be observed in the MOX fuel region. The calculated results tend to underestimate the measured one slightly in the UO$$_2$$ fuel regions. However, the dependence on the libraries is not seen.

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