Abstract
This paper presents analytical models, procedure, and results of a sensitivity study performed to investigate how the Safety Relief Valves (SRV) response of the steel containment of a Boiling Water Reactor (BWR) Mark III plant is influenced by the high frequency energy or noise associated with the idealized bubble forcing function. Various possible structural modifications to those plants already designed to have a steel containment are also presented and discussed with regard to minimizing the dynamic effects of SRV discharge loads. Special attention is given to the concept of filling concrete in the annulus between the steel containment and the shield building. The dynamic analyses of the containment structures with and without concrete in the annulus were performed and the results compared. Throughout the paper, several aspects of the SRV dynamic problem are emphasized and the relevant areas are identified for further investigations and studies.
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