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For the development of next generation reactor which is remarkably safer than existing plants, the operability of passive safety systems should be studied and its applicability to the next generation reactor should be evaluated. The purposes of this study are to evaluate the characteristics of various passive safety systems and provide the proper data for the future design with performing experiments and developing analytical methodology. Thus in this period, the following techniques for small reactors and passive safety systems subject to this study are evaluated and a part of basic experiments and numerical works necessary to the experiments were performed. First, heat pipes used in safe guard vessel which removes heat by passive means during accidents, second, natural circulation characteristics for the passive safety analysis of integrated reactor, third, helical-coiled once-through steam generator in integrated reactor, fourth, hydraulic valve for the effective function of density lock in passive decay heat removal systems, and the last is the determination of the improved source term for the integral reactor, which is the first step in the analysis of the integrated safety and the environmental impacts of nuclear power plant. summarized. (author). 172 refs., 22 figs., 23 tabs.