Analytical and experimental Mark I boiling water reactor containment safety research at the Lawrence Livermore Laboratory

An overview of research work is discussed here which adresses both large scale experimental and multidimensional analytical containment studies conducted at the Lawrence Livermore Laboratory since 1976. The Mark I Boiling Reactor (BWR) containment design is the subject of interest. In the experimental program, particular focus is placed on quantification of loss-off-coolant-accident (LOCA) induced loads. The focus of the analytical effort is toward understanding of fluid/structure interaction effects due both to LOCA induced loads and safety relief value (SRV) loads in the Mark I BWR pressure suppression wetwell (a segmented torus). (orig.)