Published 1975 | Version v1
Book

On the structural behavior of pressurized pipings under excessive-stresses caused by earthquake loadings

  • 1. Tokyo Univ. (Japan)
  • 2. Japan Atomic Energy Research Inst., Tokyo
  • 3. Tokyo Univ. (Japan). Inst. of Industrial Science

Description

There has been much discussion concerning the method of stress evaluation for the primary stress under seismic loading in Japan. To resolve this problem, the sub-committee of Japan Electric Association performed experiments in a series of 'Study on Limit Design of Nuclear Energy Facility under Earthquake' from 1971 to 1973. The main purpose of this experiment is to evaluate the safety margin to the allowable stress of 'Faulted Condition' in NB 3656.2, Appendix F-1360, of ASME Code Section III. The results show that an allowable value described in ASME Section III is conservative having a margin by 1.3 to approximately 8.3 to the 3.0 Sm limit and pipe material still remain in an elastic behavior. (Auth.)

Additional details

Publishing Information

Publisher
North-Holland.
Imprint Place
Amsterdam, The Netherlands
Imprint Title
Structural mechanics in reactor technology
Imprint Pagination
v. 4 p. K7/5 1-10.

Conference

Title
3. international conference on structural mechanics in reactor technology.
Dates
1 Sep 1975.
Place
London, UK.