Published 1993 | Version v1
Book Metadata-only

Forced vibration tests on the reactor building of the prototype FBR Monju

Creators

  • 1. Power Reactor and Nuclear Fuel Development Corporation (Japan)
  • 2. Japan Atomic Company, Tokyo (Japan)
  • 3. Obayashi Corporation, Tokyo (Japan)

Description

Power Reactor and Nuclear Fuel Development Corporation's reactor, Monju, is a prototype Fast Breeder Reactor (FBR) power plant (280 MWe). This paper reports the results of forced vibration tests on the reactor building at this plant, a vibration test simulation, and an evaluation of aseismic safety. The tests were performed with two 10-ton vibration generators when the building was almost completed. The evaluation is based on an earthquake response analysis taking account of the weight condition of the building during plant operation and the strain level during earthquake. (author)

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. 319-324

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
36028417
Subject category
S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINMENT BUILDINGS; EARTHQUAKES; MECHANICAL TESTS; MECHANICAL VIBRATIONS; MONJU REACTOR; SAFETY ANALYSIS; SAFETY STANDARDS; SEISMIC ISOLATION; SPECTRAL RESPONSE
Descriptors DEC
BREEDER REACTORS; BUILDINGS; CONTAINMENT; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS TESTING; POWER REACTORS; REACTORS; SEISMIC EVENTS; SODIUM COOLED REACTORS; STANDARDS; TESTING

Optional Information

Notes
6 figs, 2 tabs