Published 1988 | Version v1
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Analysis and test correlation of the response of the multiple support piping systems

  • 1. Nuclear Power Division Ishikawajima-Harima Heavy Industries Co., Ltd. (IHI), Yokohama (Japan)
  • 2. National Research Center for Disaster Prevention (NRCDP), Ibaraki (Japan)

Description

One of the current topics in the seismic design of the piping system is an overall reliability of the piping system in seismic durations. Actual piping systems are generally supported by independent structures such as vessels and structures. So, it is very important to clarify the behavior and to predict the maximum responses of the piping during the seismic events. This study was carried out in two phases. In the first phase, an experimental study was conducted to clarify the dynamic characteristics of the piping systems. In the test, 4B/8B inch diameter * 21m length 3-dimensional piping model was set on the large frame structure. It was excited by four hydraulic actuators using sinusoidal wave and seismic wave. To assess the computational methods of the linear system subjected to multiple support excitations, a linear dynamic analysis was carried out. In the second phase, the test was repeated with a piping having a crack. The test has been completed and data reduction is under way. This paper presents the results of the experimental study and the dynamic analysis of the multiple excitation problems in the phase one. (author)

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Part of:
International ENEA/ISMES/ENS specialist meeting on 'On-site experimental verification of the seismic behaviour of nuclear reactor structures and components'. Proceedings

Additional details

Publishing Information

Imprint Title
International ENEA/ISMES/ENS specialist meeting on 'On-site experimental verification of the seismic behaviour of nuclear reactor structures and components'. Proceedings
Imprint Pagination
430 p.
Journal Page Range
p. 275-284
Report number
INIS-XA-N--006

Conference

Title
International ENEA/ISMES/ENS specialist meeting on 'On-site experimental verification of the seismic behaviour of nuclear reactor structures and components'
Dates
4-7 May 1987
Place
Bologna-Brasimone (Italy)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
35048660
Subject category
S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
DYNAMIC LOADS; EXPERIMENTAL DATA; MECHANICAL VIBRATIONS; PIPES; RELIABILITY; SEISMIC EFFECTS; SEISMIC EVENTS; SEISMIC WAVES
Descriptors DEC
DATA; INFORMATION; NUMERICAL DATA; TUBES

Optional Information

Notes
9 refs, 11 figs, 4 tabs