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Title: Seismic fragility analysis of buried steel piping at P, L, and K reactors

Abstract

Analysis of seismic strength of buried cooling water piping in reactor areas is necessary to evaluate the risk of reactor operation because seismic events could damage these buried pipes and cause loss of coolant accidents. This report documents analysis of the ability of this piping to withstand the combined effects of the propagation of seismic waves, the possibility that the piping may not behave in a completely ductile fashion, and the distortions caused by relative displacements of structures connected to the piping.

Authors:
Publication Date:
Research Org.:
Westinghouse Savannah River Co., Aiken, SC (United States)
Sponsoring Org.:
USDOE; USDOE, Washington, DC (United States)
OSTI Identifier:
5210382
Report Number(s):
WSRC-RP-89-1277
ON: DE92015064
DOE Contract Number:
AC09-89SR18035
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; K REACTOR; SEISMIC EFFECTS; L REACTOR; P REACTOR; DYNAMIC LOADS; GROUND MOTION; LOSS OF COOLANT; PIPES; REACTOR COOLING SYSTEMS; REACTOR SAFETY; SEISMIC WAVES; WAVE PROPAGATION; ACCIDENTS; COOLING SYSTEMS; HEAVY WATER MODERATED REACTORS; MOTION; PRODUCTION REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; SPECIAL PRODUCTION REACTORS; 220900* - Nuclear Reactor Technology- Reactor Safety; 220600 - Nuclear Reactor Technology- Research, Test & Experimental Reactors

Citation Formats

Wingo, H.E.. Seismic fragility analysis of buried steel piping at P, L, and K reactors. United States: N. p., 1989. Web. doi:10.2172/5210382.
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Wingo, H.E.. Seismic fragility analysis of buried steel piping at P, L, and K reactors. United States. doi:10.2172/5210382.
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Wingo, H.E.. Sun . "Seismic fragility analysis of buried steel piping at P, L, and K reactors". United States. doi:10.2172/5210382. https://www.osti.gov/servlets/purl/5210382.
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@article{osti_5210382,
title = {Seismic fragility analysis of buried steel piping at P, L, and K reactors},
author = {Wingo, H.E.},
abstractNote = {Analysis of seismic strength of buried cooling water piping in reactor areas is necessary to evaluate the risk of reactor operation because seismic events could damage these buried pipes and cause loss of coolant accidents. This report documents analysis of the ability of this piping to withstand the combined effects of the propagation of seismic waves, the possibility that the piping may not behave in a completely ductile fashion, and the distortions caused by relative displacements of structures connected to the piping.},
doi = {10.2172/5210382},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Sun Oct 01 00:00:00 EDT 1989},
month = {Sun Oct 01 00:00:00 EDT 1989}
}
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Technical Report:
View Technical Report (1.24 MB)
DOI:  10.2172/5210382
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  • Analysis of seismic strength of buried cooling water piping in reactor areas is necessary to evaluate the risk of reactor operation because seismic events could damage these buried pipes and cause loss of coolant accidents. This report documents analysis of the ability of this piping to withstand the combined effects of the propagation of seismic waves, the possibility that the piping may not behave in a completely ductile fashion, and the distortions caused by relative displacements of structures connected to the piping.

  • This report presents the results of the seismic evaluation of three piping systems located in Reactor Building 105-L at the Savannah River Plant near Aiken, South Carolina. The analysis was performed for E.I. du Pont de Nemours and Company (Du Pont) for the seismic qualification of the piping systems, according to the 1967 Housner criteria, and to recommend actions, which should be taken by Du Pont, to ensure the complete seismic adequacy of these systems. The following systems were analyzed: confinement heat removal system (CHRS); process water system (PWS); and modified cross-tie header system (CTHS).

  • ; ;
    The specimen studied was a half-scale model of a piping system from a nuclear reactor power plant. This was tested in its original design configuration using mechanical shock arrestors (snubbers), and subsequently in a revised configuration using ductile steel energy absorbers. The influence of the snubbers and of different energy absorbers on the dynamic response of the pipe system is discussed; a direct one-to-one replacement of the snubbers by energy absorbers allows a direct comparison of the results. The response of the structure was studied under all three direction components of ground motions, though a maximum of two components (onemore » horizontal and the vertical) was applied simultaneously. In the case of the energy absorbers, the effect of a thermal loading was simulated by a deforming system at the restrainers, and the seismic loading was superimposed on this biased configuration. Over a hundred test runs were recorded using four different artificial earthquakes as well as sinusoidal input. A study of damping behavior, frequency spectra and hysteresis loops for both shock arrestors and energy absorbers facilitates an extensive interpretation of the experimental data.« less

  • ; ; ; ...
    This Fragility Analysis is the third of three volumes for the Seismic Margin Review of the Maine Yankee Atomic Power Station. Volume 1 is the Summary Report of the first trial seismic margin review. Volume 2, Systems Analysis, documents the results of the systems screening for the review. The three volumes are part of the Seismic Margins Program initiated in 1984 by the Nuclear Regulatory Commission (NRC) to quantify seismic margins at nuclear power plants. The overall objectives of the trial review are to assess the seismic margins of a particular pressurized water reactor, and to test the adequacy ofmore » this review approach, quantification techniques, and guidelines for performing the review. Results from the trial review will be used to revise the seismic margin methodology and guidelines so that the NRC and industry can readily apply them to assess the inherent quantitative seismic capacity of nuclear power plants.« less

  • ;
    This report presents a seismic fragility analysis of equipment and structures in an electric substation in Memphis, Tennessee. These include the pothead structure, 115 kv switch structure, 97 kv lightning arresters, control house, capacitor banks, 115/12 kv transformers, 12 kv regulators, 115 kv oil circuit breakers, and 12 kv oil circuit breakers. The results from this fragility analysis provide the expected performance of equipment and structures in a substation. They can also be used to evaluate the seismic performance of the entire electric substation and to perform a system reliability analysis of the electric transmission system.