Experiments of Self-wastage Phenomena Elucidation in Steam Generator Tube of Sodium-cooled Fast Reactor-Reference-Cited by-同舟云学术

Experiments of Self-wastage Phenomena Elucidation in Steam Generator Tube of Sodium-cooled Fast Reactor

Published:2020 Issue:4 Volume:19 Page:234-244
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:

UMEDA Ryota¹,SHIMOYAMA Kazuhito¹,KURIHARA Akikazu¹

Affiliation:

1. 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/19/4/19_J19.012/_pdf

Reference8 articles.

1. 1) H. Tanabe, K. Aoto, H. Ito et al., “Sodium technology handbook,” Jpn. Nucl. Cycle Devel. Insti. (2005), [in Japanese].

2. 2) M. Usami, K. Shimoyama, H. Tanabe et al., “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) Y. Abe, K. Shimoyama, A. Kurihara, Development of Experimental Method for Self-wastage Behavior in Sodium-water Reaction, -Development of Test Rig (SWAT-2R) and Study for Exerimental Procedure JAEA-Technology 2014-026, Japan Atomic Energy Agency (2014), [in Japanese].

4. 4) K. Shimoyama, H. Tanabe, Y. Himeno, Self-Wastage Behavior of High-Chromium Content Steel for FBR Steam Generator Tube, -Studies of Micro-Leak Sodium-Water Reactions (4) PNC-TN9410 88-140, Power Reactor and Nuclear Fuel Development Corporation (1988), [in Japanese].

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