Study on Target wastage for Sodium-water Reaction Environment Formed on Periphery of Adjacent Tube in Steam Generator of Sodium-cooled Fast Reactor　Composite Oxidation-Type Corrosion with Flow Experiment using High-temperature Sodium Hydroxide-Reference-Cited by-同舟云学术

Study on Target wastage for Sodium-water Reaction Environment Formed on Periphery of Adjacent Tube in Steam Generator of Sodium-cooled Fast Reactor　Composite Oxidation-Type Corrosion with Flow Experiment using High-temperature Sodium Hydroxide

Published:2015 Issue:4 Volume:14 Page:235-248
ISSN:1347-2879
Container-title:Transactions of the Atomic Energy Society of Japan
language:en
Short-container-title:Transactions of the Atomic Energy Society of Japan

Author:

KURIHARA Akikazu¹,UMEDA Ryota¹,KIKUCHI Shin²,SHIMOYAMA Kazuhito¹,OHSHIMA Hiroyuki²

Affiliation:

1. Oarai Research and Development Center, Japan Atomic Energy Agency

2. Advanced Fast Reactor Cycle System Research and Development Center, Japan Atomic Energy Agency

Publisher

Atomic Energy Society of Japan

Subject

Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Link

https://www.jstage.jst.go.jp/article/taesj/14/4/14_J14.038/_pdf

Reference15 articles.

1. 1) H. Tanabe, M. Kuroha, Y. Himeno, “Safety Research on FBR steam generator,” Genshiryokukougyou (Nikkan-Kogyo Shimbun, Ltd.), 34[1], 69-76 (1988), [in Japanese].

2. 2) M. Usami, K. Shimoyama, H. Tanabe, Y. Himeno, “Wastage characteristics of high-chrome steels under sodium-water reaction,” Nihon-Genshiryoku-Gakkai-Shi (J. At. Energy Soc. Jpn.), 33[4], 363-372 (1991), [in Japanese].

3. 3) A. Uchibori, H. Ohshima, “Numerical methods for compressible multiphase flow with sodium-water chemical reaction,” J. Power Energy Syst., 7[2], 106-121 (2013).

4. 4) S. Kikuchi, H. Seino, A. Kurihara, H. Ohshima, “Kinetic study of sodium-water surface reaction by differential thermal analysis,” J. Power Energy Syst., 7[2], 79-93(2013).

5. 5) M. Nishimura, K. Shimoyama, A. Kurihara, H. Seino, Sodium-water Reaction Test to Confirm Influence on Heat Transfer Tubes, JNC TN9400 2003-014, Japan Nuclear Cycle Development Institute (2003), [in Japanese].

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