Art

J-GLOBAL ID：201202284834629947   Reference number：12A0607711

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

日本のナトリウム冷却高速増殖炉の一次冷却システムの放射性腐食生成物のシミュレーション

Author (5)： MATUO Youichirou (Japan Atomic Energy Agency) ,  MATUO Youichirou (Res. Inst. of Nuclear Engineering, Univ. of Fukui) ,  MIYAHARA Shinya (Japan Atomic Energy Agency) ,  MIYAHARA Shinya (Res. Inst. of Nuclear Engineering, Univ. of Fukui) ,  IZUMI Yoshinobu (Res. Inst. of Nuclear Engineering, Univ. of Fukui)
Material： Journal of Power and Energy Systems (Web)  (J Power Energy Syst (Web))
Volume： 6  Issue： 1  Page： 6-17 (J-STAGE)  Publication year： 2012 
JST Material Number： U0041A  ISSN： 1881-3062  Document type： Article
Article type： 原著論文  Country of issue： Japan (JPN)  Language： ENGLISH (EN)

Thesaurus term： *liquid metal cooled reactor ,  FBR type reactor ,  reactor coolant ,  *reactor cooling system ,  *corrosion product ,  *exposure dose ,  LMFBR type reactor ,  *computer code ,  management area ,  Joyo reactor ,  sodium cooled type reactor
Semi thesaurus term： sodium-cooled reactor ,  fast breeder reactor ,  reactor coolant system ,  radiation exposure dose ,  computer code

JST classification (1)： Research and development  (MA01040L)

Reference (24)：

• (1) K. Iizawa, et al.: “Calculational model and code for corrosion product behavior in primary circuits of LMFBRs”, Proc. International Working Group on Fast Reactors (IWGFR/64), may 5-8 (1987) pp.191-225
• (2) K. Iizawa, et al.: “Study on Radioactive Corrosion Products Behaviour in Primary Circuits of JOYO”, Proc. International Working Group on Fast Reactors (IWGFR/64), may 5-8 (1987) pp.227-255
• (3) Y. Matuo, et al.: Prediction of radioactive corrosion product transfer in primary systems of Japanese prototype fast breeder reactor MONJU” Proc. International Conference on Nuclear Engineering, Xi-an, ICONE18-29171, (2009)
• (4) Y. Matuo, et al.: “Transport of Radioactive Corrosion Products in Primary System of Sodium-Cooled Fast Breeder Reactor “MONJU” ” Journal of Power and Energy Systems, 5 (2011) pp.96-107
• (5) K. Iizawa, et al.: “Development of DOSE Rate Estimation System for FBR Maintenance” JNC Technical Review, 12, (2001) pp.21-36 (In Japanese)

Terms in the title (7)： 日本 ,  ナトリウム ,  高速増殖炉 ,  冷却システム ,  放射性 ,  腐食生成物 ,  シミュレーション