Evaluation of conservativism in the simplified elastic-plastic analysis using analytical results - Part 2 : Proposal of a new Ke-function

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

Volumn 419, Issue , 2000, Pages 33-36

  Asada, Seiji ^a   Nakamura, Takao ^b   Asada, Yasuhide ^c  

^a MITSUBISHI HEAVY INDUSTRIES LTD   (Japan)

^b KANSAI ELECTRIC POWER CO   (Japan)

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

Author keywords

[No Author keywords available]

Indexed keywords

DATA REDUCTION; PIPING SYSTEMS; PLASTIC DEFORMATION; PRESSURE EFFECTS; PRESSURE VESSEL CODES; STRAIN;

PIPING TESTS;

ELASTOPLASTICITY;

EID: 0010615409     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Review

References (6)

1. ASME Boiler and Pressure Vessel Code Section III
2. Asada, S., Nakamura, T. and Asada, Y. ,"Evaluation of Conservatism in the Simplified Elastic-Plastic Analysis Using Analytical Results," Pressure Vessel and Piping Codes and Standards, PVP-Vol.407, The American Society of Mechanical Engineers, pp.255-262, 2000
3. Yokota, H., et. al., "Study on Seismic Design of Nuclear Power Plant Piping in Japan, Part 1:Overview of the Study," Pressure Vessel and Piping Codes and Standards, PVP-Vol.407, The American Society of Mechanical Engineers, pp. 117-123, 2000
4. Yokota, H., et. al., "Study on Seismic Design of Nuclear Power Plant Piping in Japan, Part 3:Component Tests Results," Pressure Vessel and Piping Codes and Standards, PVP-Vol.407, The American Society of Mechanical Engineers, pp.131-137, 2000
5. MITI Notification 501, 1980 and 1994, "Technical Standard for Construction of Nuclear Power plant Components", in Japanese
6. USA Standard B31.7, Nuclear Power Piping, 1969