Transport of Radioactive Corrosion Products in Primary System of Sodium-Cooled Fast Breeder Reactor "MONJU"-Reference-Cited by-同舟云学术

Transport of Radioactive Corrosion Products in Primary System of Sodium-Cooled Fast Breeder Reactor "MONJU"

Published:2011 Issue:1 Volume:5 Page:96-107
ISSN:1881-3062
Container-title:Journal of Power and Energy Systems
language:en
Short-container-title:JPES

Author:

MATUO Youichirou¹,HASEGAWA Masanori²,MAEGAWA Yoshiharu²,MIYAHARA Shinya¹

Affiliation:

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

2. Japan Atomic Energy Agency

Publisher

Japan Society of Mechanical Engineers

Link

http://www.jstage.jst.go.jp/article/jpes/5/1/5_1_96/_pdf

Reference13 articles.

1. (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. (2) F. Masse et al.: “Activation, Corrosion and Contamination in Fast Breeder Reactors - Validation of Model with Experimental Data” Material Bahaviour and Physical Chemistry in Liquid Metal Systems 2 (1995) pp.35-46

3. (3) 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

4. An analysis of radioactive corrosion product transfer in sodium loop systems

5. (5) W. L. Kuhn,: “A Computational Technique for Estimating Corrosion Product Release in an LMFBR” Proc. International Conference on Liquid Metal Technology in Energy Production (1976) pp.280-283

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1. Simulation of Radioactive Corrosion Product in Primary Cooling System of Japanese Sodium-Cooled Fast Breeder Reactor;Journal of Power and Energy Systems;2012