Simulation of Radioactive Corrosion Product in Primary Cooling System of Japanese Sodium-Cooled Fast Breeder Reactor

スポンサーリンク

概要

• 論文の詳細を見る

• Radioactive Corrosion Product (CP) is a main cause of personal radiation exposure during maintenance with no breached fuel in fast breeder reactor (FBR) plants. The most important CP is <SUP>54</SUP>Mn and <SUP>60</SUP>Co. 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. The C/E (calculated / experimentally observed) value for CP deposition was improved through use of this improved PSYCHE incorporating the Particle Model. Moreover, among the percentage of total radioactive deposition accounted for by CP in particle form, <SUP>54</SUP>Mn was estimated to constitute approximately 20 % and <SUP>60</SUP>Co approximately 40 % in the cold-leg region. These calculation results are consistent with the measured results for the actual cold-leg piping in the JOYO.

著者

• MATUO Youichirou

  Japan Atomic Energy Agency, Research Institute of Nuclear Engineering, University of Fukui

• MIYAHARA Shinya

  Japan Atomic Energy Agency

• IZUMI Yoshinobu

  Research Institute of Nuclear Engineering, University of Fukui

• MATUO Youichirou

  Japan Atomic Energy Agency

関連論文

• Transport of Radioactive Corrosion Products in Primary System of Sodium-Cooled Fast Breeder Reactor “MONJU”
• Experimental Investigation of Lead-Bismuth Evaporation Behavior
• Reactive Wetting of Metallic Plated Steels by Liquid Sodium
• Simulation of Radioactive Corrosion Product in Primary Cooling System of Japanese Sodium-Cooled Fast Breeder Reactor

スポンサーリンク