Published April 1978 | Version v1
Report Restricted

Vibration tests of a commercial gas cooled reactor core

  • 1. Shimizu Construction Co. Ltd., Tokyo

Description

In the seismic design of a nuclear power plant, the structures and equipments of the plant including foundation soil are represented by an equivalent mathematical model, and the deflections and stresses during earthquake are analyzed. In the analysis, the dynamic properties of various elements that influence on the dynamic behavior of the plant are examined. The damping constant assumed in the analysis plays an important role to determine the response amplitude of core. The effect of damping may even be more important than the effects of stiffness, mass, and other factors for the determination of the amplitude of core response. The damping has been generally assumed to take a value within a range from 1 to 5% of the critical from our empirical judgment for ordinary structures. However, these two extreme values lead to two or three times difference between the peak amplitudes of the response. Because the damping is not accurately known, it has been common practice to take a conservative value, generally less than 2% for the dynamic analyses of core. This is undesirable from the economical point of view if the damping is estimated too little. Under those circumstances, much attention of the persons concerned had been directed toward obtaining a right knowledge of the damping characteristics of core. That became a direct motive to scheme and practice the full scale model test for the commercial gas cooled reactor core that was under construction at Hunterston in Scotland. This experiment was carried out August 1972 in cooperation with the Nuclear Power Group Ltd. in United Kingdom, Fuji Electric Co. Ltd. and Shimizu Construction Co. Ltd. in Japan

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Additional details

Publishing Information

Imprint Title
Proceedings of the Japan--U.S. seminar on HTGR safety technology. Volume 1. Seismic research
Journal Page Range
p. 114-125.
Report number
BNL-NUREG--50689(Vol.1)

Conference

Title
Seminar on HTGR safety technology.
Dates
15 - 16 Sep 1977.
Place
Upton, NY, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10441442
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AGR TYPE REACTORS; HTGR TYPE REACTORS; MECHANICAL VIBRATIONS; REACTOR CORES; RESPONSE FUNCTIONS; SEISMIC EFFECTS; SIMULATION
Descriptors DEC
ENRICHED URANIUM REACTORS; FUNCTIONS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; REACTOR COMPONENTS; REACTORS