Study on seismic design of nuclear power plant piping in Japan Part 3 ; Component Tests Results

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

Volumn 407, Issue , 2000, Pages 131-137

  Yoshino, Kouichi ^a,b   Sakakida, Takaaki ^c   Yokota, Hiroshi ^d   Asada, Yasuhide ^e   Endou, Rokurou ^f   Fujiwaka, Tatsuya ^g   Suzuki, Kohei ^h  

^a TOSHIBA CORPORATION   (Japan)

^b Hitachi Ltd ^*  (Japan)

^c HITACHI LTD   (Japan)

^d MITSUBISHI HEAVY INDUSTRIES LTD   (Japan)

^e CENTRAL RESEARCH INSTITUTE OF ELECTRIC POWER INDUSTRY   (Japan)

^f Mitoshiro Bldg   (Japan)

^g IHI CORPORATION   (Japan)

^h TOKYO METROPOLITAN UNIVERSITY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 0000872420     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Article

References (4)

1. NRC, 1998, Seismic Analysis of Piping Final Program Report, NUREG/CR-5361
2. ASME, 1994, Boiler and Pressure Vessel Code, Section III Division I
3. L. F. Coffin, 1970, "The Deformation and Fracture of a Ductile Metal Under Superimposed Cyclic and Monotonic Strain", ASTM STP 467, pp.53-76
4. Y. Asada, 1985, "Failure Criterion on Low-Cycle Fatigue with Excessive Progressive Deformation", Proceedings of 3rd German-Japan Joint Seminar II 2.2, pp.1-13