Published 1993 | Version v1
Book

Variation of non-linear response of reactor building considering uncertainties of dynamic properties

  • 1. Nuclear Facilities Dept., Taisei Corporation (Japan)
  • 2. Dept. of Architecture, Tohoku University (Japan)
  • 3. Office of Energy and Nuclear Engineering, Takenaka Corp. (Japan)
  • 4. Siting Technology Dept., Nuclear Power Engineering Corp. (Japan)

Description

Study on advanced seismic design for LWR has been carried out by the Nuclear Power Engineering Corporation (NUPEC), under the sponsorship of the Ministry of International Trade and Industry (MITI) of Japan. Recently, a lot of efforts to estimate the safety integrity of a reactor building have been made by many researchers. When we evaluate the safety integrity, it is important to estimate the variation of the seismic response that is associated with the uncertainties of the dynamic properties. The object of this study is to evaluate the variation of non-linear seismic response of the reactor buildings. In this study, several non-linear variation analyses are carried out on two typical types (BWR type and PWR type) of reactor buildings in Japan, focusing on two points. One is to use statistical data based on laboratory tests and field tests to simulate the real phenomena and second is to deal with the maximum variation of the non-linear response nearby the second yield point of the tri-linear restoring force curve

Part of:
Transactions of the 12. international conference on Structural Mechanics in Reactor Technology (SMiRT). Volume K1: Seismic response analysis and design

Additional details

Publishing Information

Publisher
Elsevier
Imprint Place
Amsterdam (Netherlands)
ISBN
0-444-81515-5
Imprint Title
Transactions of the 12. international conference on Structural Mechanics in Reactor Technology (SMiRT). Volume K1: Seismic response analysis and design
Imprint Pagination
398 p.
Journal Page Range
p. 265-270

Conference

Title
12. international conference on Structural Mechanics in Reactor Technology
Acronym
SMiRT 12
Dates
15-20 Aug 1993
Place
Stuttgart (Germany)

INIS

Country of Publication
Netherlands
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
36028408
Subject category
S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; DYNAMIC LOADS; FREQUENCY RESPONSE TESTING; MECHANICAL TESTS; NONLINEAR PROBLEMS; PWR TYPE REACTORS; SAFETY STANDARDS; SEISMIC EFFECTS; SEISMIC ISOLATION
Descriptors DEC
ENRICHED URANIUM REACTORS; MATERIALS TESTING; POWER REACTORS; REACTORS; STANDARDS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
2 refs, 8 figs, 1 tab