![]() ![]() The approach pressented is justified to be a workable system for a new plant design. The results of the analyses have shown the proposed stress criteria are satisfied. Finite element analyses are performed by using ASHSD2 and EASE2 computer codes. This approach warrants an early erection of the shield building and a late installation of piping systems in the containment vessel suppression pool area. The system is physically separated from the shield building. A composite action is assumed between the steel containment vessel shell and the concrete section. A concrete backing configuration in the suppression pool area of Mark III Containment is proposed in this paper. ![]() Parametric studies indicated that a substantial reduction in response can be obtained by increasing the stiffness of the steel containment vessel in the lover area. Extremely high spectral peak accelerations of the free-standing steel containment vessel can be obtained during the air dearing process of the S/RV discharge. ![]() The lower portion of the containment vessel serves as a suppression pool pressure boundary and is designed to sustain the effects of postulated loss of coolant accidents, seismic occurrences, S/RV discharge loads, and other effects. For a plant in the construction stage, extensive modifications will be made to qualify these new loads. Recently, engineers have been considering the significant dynamic impact of safety/relief valve (S/RV) discharge loads on the containment structures, safety equipment, and piping systems in BWR type reactors. International Nuclear Information System (INIS) Mark III Containment vessel/annulus concrete design ![]()
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