Development of numerical analysis code LEAP-III for tube failure propagation

Author:

UCHIBORI Akihiro1,YANAGISAWA Hideki2,TAKATA Takashi1,OHSHIMA Hiroyuki1

Affiliation:

1. Japan Atomic Energy Agency

2. NESI Corporation

Publisher

Japan Society of Mechanical Engineers

Reference7 articles.

1. Hamada, H. and Tanabe, H., A study of the selection of rational design basic leak – modification and analysis of the LEAP code –, PNC-TN9410 92-097 (1992) (in Japanese).

2. Japanese Industrial Standards, Construction of pressure vessel-General principles, JIS B 8265 (2010) (in Japanese).

3. Kato, S., Yoshida, E. and Aoto, K., Ultra-high temperature strength properties on Mod.9Cr-1Mo steel, JNC-TN9400 2000-042 (2000) (in Japanese).

4. Miyake, O., Hamada, H., Tanabe, H., Wada, Y., Miyakawa, A., Okabe, A., Nakai, R. and Hiroi, H., The development and application of overheating failure model of FBR steam generator tubes (IV), JNC-TN2400 2003-003 (2004) (in Japanese).

5. Nei, H. and Hori, M., Wastage phenomena by small leak sodium-water reaction (reacting temperature and wastage distribution), Transactions of the Japan Society of Mechanical Engineers (2nd), Vol.43, No.368 (1977), pp.1418–1425 (in Japanese).

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