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Field vibration test of principal equipment of nuclear power plants

Journal Article:

Abstract

Japan is one of the most earthquake-stricken countries in the world, and demands for aseismic design have become severer recently. In a nuclear power plant in particular, consisting of a reactor vessel and other facilities dealing with a radioactive substance in some form or other, it is essential from the standpoint of safety to eliminate any possibility of radioactive hazards for the local public, and the employees at the plant as well, if these facilities are struck by an earthquake. This paper is related to the reactor vessel, reactor primary cooling equipment and piping system and important general piping as examples of important facilities of a nuclear power plant, and discusses vibration tests of an actual plant in the field from the standpoint of enhancing the aseismic safety of the Mitsubishi PWR nuclear power plant. Especially concerning vibration test technology, the effects in the evaluation of aseismic safety and its limits are studied to prove how it contributes to the enhancement of the reliability of aseismic design of nuclear power plants.
Publication Date:
Sep 01, 1984
Product Type:
Journal Article
Reference Number:
AIX-17-022982; EDB-86-072401
Resource Relation:
Journal Name: Mitsubishi Juko Giho; (Japan); Journal Volume: 21:5
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; NUCLEAR POWER PLANTS; DESIGN; REACTOR SAFETY; SEISMIC EFFECTS; BUILDINGS; CONTAINMENT SHELLS; FREQUENCY DEPENDENCE; JAPAN; MECHANICAL VIBRATIONS; PIPES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; QUALITY ASSURANCE; RELIABILITY; RESPONSE FUNCTIONS; STRESSES; ASIA; CONTAINMENT; COOLING SYSTEMS; ENERGY SYSTEMS; FUNCTIONS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; THERMAL POWER PLANTS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled
OSTI ID:
5903414
Research Organizations:
Mitsubishi Heavy Industries Ltd., Tokyo, Japan
Country of Origin:
Japan
Language:
Japanese
Other Identifying Numbers:
Journal ID: CODEN: MIJGA
Submitting Site:
INIS
Size:
Pages: 645-653
Announcement Date:

Journal Article:

Citation Formats

Shiraki, Kazuhiro, Fujita, Katsuhisa, Kajimura, Motohiko, Ikegami, Yasuhiko, Hanzawa, Katsumi, Sakai, Yoshiyuki, Kokubo, Eiji, and Igarashi, Shigeru. Field vibration test of principal equipment of nuclear power plants. Japan: N. p., 1984. Web.
Shiraki, Kazuhiro, Fujita, Katsuhisa, Kajimura, Motohiko, Ikegami, Yasuhiko, Hanzawa, Katsumi, Sakai, Yoshiyuki, Kokubo, Eiji, & Igarashi, Shigeru. Field vibration test of principal equipment of nuclear power plants. Japan.
Shiraki, Kazuhiro, Fujita, Katsuhisa, Kajimura, Motohiko, Ikegami, Yasuhiko, Hanzawa, Katsumi, Sakai, Yoshiyuki, Kokubo, Eiji, and Igarashi, Shigeru. 1984. "Field vibration test of principal equipment of nuclear power plants." Japan.
@misc{etde_5903414,
title = {Field vibration test of principal equipment of nuclear power plants}
author = {Shiraki, Kazuhiro, Fujita, Katsuhisa, Kajimura, Motohiko, Ikegami, Yasuhiko, Hanzawa, Katsumi, Sakai, Yoshiyuki, Kokubo, Eiji, and Igarashi, Shigeru}
abstractNote = {Japan is one of the most earthquake-stricken countries in the world, and demands for aseismic design have become severer recently. In a nuclear power plant in particular, consisting of a reactor vessel and other facilities dealing with a radioactive substance in some form or other, it is essential from the standpoint of safety to eliminate any possibility of radioactive hazards for the local public, and the employees at the plant as well, if these facilities are struck by an earthquake. This paper is related to the reactor vessel, reactor primary cooling equipment and piping system and important general piping as examples of important facilities of a nuclear power plant, and discusses vibration tests of an actual plant in the field from the standpoint of enhancing the aseismic safety of the Mitsubishi PWR nuclear power plant. Especially concerning vibration test technology, the effects in the evaluation of aseismic safety and its limits are studied to prove how it contributes to the enhancement of the reliability of aseismic design of nuclear power plants.}
journal = {Mitsubishi Juko Giho; (Japan)}
volume = {21:5}
journal type = {AC}
place = {Japan}
year = {1984}
month = {Sep}
}