Design and modification of steam generator safety system of FBR MONJU

Nuclear Engineering and Design

Volumn 237, Issue 12-13, 2007, Pages 1419-1428

  Matsuura, Makoto ^a   Hatori, Masakazu ^a   Ikeda, Makinori ^a  

^a JAPAN ATOMIC ENERGY AGENCY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

LEAK DETECTION; PRESSURE GAGES; REACTION KINETICS; RUPTURE DISKS; STEAM GENERATORS; STRUCTURAL INTEGRITY;

FAST BREEDER REACTOR (FBR); SAFETY ASSESSMENT; SODIUM COOLED REACTORS; SODIUM WATER REACTION;

BREEDER REACTORS;

EID: 34249913738     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2006.09.046     Document Type: Article

References (6)

1. A.M. Judd The under-sodium leak in the PFR superheater 2, Feb. 1987 Nucl. Energy 31 3 1992
2. H. Hamada H. Tanabe Y. Wada A. Miyakawa H. Hiroi Study of overheating rupture for FBR steam generators Proceedings of Eighth International Conference on Nuclear Engineering (ICONE 8), ICONE-8240 2000
3. Itou, I., Moriyama, M., Maeda, H., 1998. Improving the safety and reliability of MONJU, JNC Technical Review, No. 1, December, pp. 7–18.
4. K. Itoh K. Onuki K. Tomobe S. Taniyama Replacement of the drain system of secondary circuit at MONJU Proceedings of 11th International Conference on Nuclear Engineering (ICONE 11), ICONE11-36072 2003
5. Miyake, O., Hamada, H., Tanabe, H., Wada, Y., Miyakawa, A., Okabe, A., Nakai, R., Hiroi, H., 2003. The development and application of overheating failure model of FBR steam generator tubes (IV), JNC TN2400 2003-003.
6. R. Currie The under sodium leak in the PFR superheater 2, Feb. 1987 Proceedings of the Specialists’ Meeting on SG Failure and Failure Propagation Experience IWGFR/IAEA, France 1990