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[en] This paper describes the use of a relatively simple parametric model to estimate containment loads following an ex-vessel steam spike. The study was motivated because several PSAs have identified containment loads accompanying reactor vessel failures as a major contributor to early containment failure. The paper includes a detailed description of the simple but physically sound parametric model which was adopted to estimate containment loads following a steam spike into the reactor cavity. (author)
Source
International Atomic Energy Agency, Vienna (Austria); 127 p; ISSN 1011-4289; 
; Mar 1998; p. 37-43; Technical committee meeting on use of PSA Level 2 analysis for improving containment performance; Vienna (Austria); 9-13 Dec 1996; 3 refs, 3 figs.
; Mar 1998; p. 37-43; Technical committee meeting on use of PSA Level 2 analysis for improving containment performance; Vienna (Austria); 9-13 Dec 1996; 3 refs, 3 figs.