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AbstractAbstract
[en] This paper presents the results of a numerical stress analysis performed for the disk and seat region of the 30 in. main steam check valve installed in a nuclear power station. The stresses and strains are predicted subsequent to a postulated rupture in the main steam line between the steam generator and the containment isolation valve. This study was prompted by the existence of extreme impact forces generated by closure of the check valve under the postulated rupture. This analysis was undertaken to determine the extent of inelastic behavior. (Auth.)
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Jaeger, T.A. (comp.) (Bundesanstalt fuer Materialpruefung, Berlin (Germany, F.R.)); International Association for Structural Mechanics in Reactor Technology; Commission of the European Communities, Brussels (Belgium); British Nuclear Energy Society, London; v. 2 p. F4/9 1-13; 1975; North-Holland; Amsterdam, The Netherlands; 3. international conference on structural mechanics in reactor technology; London, UK; 1 Sep 1975
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Conference
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