applied example MCNP5 on skyshine of nuclear facility

Zaima, Naoki; Naganuma, Masaki; Sakao, Ryota; Tokizawa, Takayuki

no journal, , 

In the field of safety analysis on nuclear fuel facility, conventional calculation code (QAD/G33 etc.) had been used. However some confines of codes had lead overestimation. At the chance of trial for shielding or skyshine calculation, Monte Carlo transport calculation code MCNP5 was applied. The comparison between both, error estimations, model designs, several artifices will be introduced.