Simulation of radioactive corrosion product in primary cooling system of Japanese sodium-cooled fast breeder reactor

Matsuo, Yoichiro; Miyahara, Shinya  ; Izumi, Yoshinobu*

Radioactive corrosion product (CP) is a main cause of personal radiation exposure during maintenance with no breached fuel in fast breeder reactor (FBR) plants. In order to establish techniques of radiation dose estimation for radiation workers in radiation-controlled areas of the FBR, the PSYCHE (Program SYstem for Corrosion Hazard Evaluation) code was developed. We add the Particle Model to the conventional PSYCHE analytical model. In this paper, we performed calculation of CP transfer in JOYO using an improved calculation code in which the Particle Model was added to the PSYCHE code. The C/E (calculated / experimentally observed) value for CP deposition was improved through use of this improved PSYCHE code incorporating the Particle Model.