Calculation of radioactive corrosion product transfer in primary systems of prototype fast breeder reactor MONJU

Matsuo, Yoichiro; Hasegawa, Masanori; Maegawa, Yoshiharu; Miyahara, Shinya  

In order to reduce the personal radiation exposure during maintenance, the CPs transport behavior analysis code "PSYCHE" has been developed. The density of each deposited CP of primary coolant system in MONJU was estimated by using the PSYCHE. Moreover, the calculation result in the case that PNC and T-T equation for corrosion rate was compared. Our results suggest that the down stream effect was important in the cobalt type.