Published 1989 | Version v1
Book

High level vibration test of nuclear power piping

  • 1. Nuclear Power Engineering Test Center, Tokyo (Japan)
  • 2. Japan Atomic Power Co., Tokyo (Japan)
  • 3. Tokyo Electric Power Co., Inc. (Japan)
  • 4. Kansai Electric Power Co., Inc., Osaka (Japan)
  • 5. Mitsubishi Heavy Industries Ltd., Takasago, Hyogo (Japan). Takasago Works
  • 6. Mitsubishi Heavy Industries Ltd., Kobe (Japan). Kobe Shipbuilding and Engine Works
  • 7. Mitsubishi Atomic Power Industries, Inc., Tokyo (Japan)
  • 8. Brookhaven National Lab., Upton, NY (USA)

Description

A series of seismic capacity tests of nuclear power piping have been performed to investigate elastic-plastic response characteristics and obtain additional data concerning the ultimate limit of a piping system subjected to earthquake excitations. The test model was designed by modifying the 1/2.5 scale model of a PWR primary coolant loop. Elastic and inelastic seismic response behavior of the test model was measured in a number of test runs with an increasing excitation input level up to the limit of the vibration table. In the maximum input condition, large dynamic plastic strains were obtained in the piping. Crack initiation was detected following the second maximum excitation run

Additional details

Additional titles

Subtitle (English)
Test procedure and test results

Publishing Information

Publisher
American Association for Structural Mechanics in Reactor Technology.
Imprint Place
Los Angeles, CA (USA)
ISBN
0-9623306-0-4
Imprint Title
Transactions of the 10th international conference on structural mechanics in reactor technology
Imprint Pagination
967 p.
Series
Seismic response analysis and design.
Journal Page Range
p. 745-750.

Conference

Title
10. international conference on Structural Mechanics in Reactor Technology (SMIRT).
Dates
14-18 Aug 1989.
Place
Anaheim, CA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
21079929
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FRACTURE MECHANICS; HAZARDS; PIPES; REACTOR COMPONENTS; REACTOR SAFETY; SEISMIC EFFECTS; TESTING
Descriptors DEC
MECHANICS; SAFETY

Optional Information

Secondary number(s)
CONF-890855--.