Transport of Radioactive Corrosion Products in Primary System of Sodium-Cooled Fast Breeder Reactor “MONJU”
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概要
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Radioactive corrosion products (CP) are primary cause of personal radiation exposure during maintenance work at FBR plants with no breached fuel. The PSYCHE code has been developed based on the Solution-Precipitation model for analysis of CP transfer behavior. We predicted and analyzed the CP solution and precipitation behavior of MONJU to evaluate the applicability of the PSYCHE code to MONJU, using the parameters verified in the calculations for JOYO. From the calculation result pertaining to the MONJU system, distribution of 54Mn deposited in the primary cooling system over 20 years of operation is predicted to be approximately 7 times larger than that of 60Co. In particular, predictions show a notable tendency for 54Mn precipitation to be distributed in the primary pump and cold-leg. The calculated distribution of 54Mn and 60Co in the primary cooling system of MONJU agreed with tendencies of measured distribution of JOYO.
著者
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MATUO Youichirou
Japan Atomic Energy Agency, Research Institute of Nuclear Engineering, University of Fukui
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HASEGAWA Masanori
Japan Atomic Energy Agency
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MAEGAWA Yoshiharu
Japan Atomic Energy Agency
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MIYAHARA Shinya
Japan Atomic Energy Agency, Research Institute of Nuclear Engineering, University of Fukui
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MIYAHARA Shinya
Japan Atomic Energy Agency
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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”
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