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- W2467442078 abstract "The concept of supercritical water cooled reactors is developed for the innovation toward cost reduction. Design and safety features of the reactor and the plant system are described. The reactor coolant system is the once-through direct-cycle. It is different from those of BWR and PWR. It is the simplest, but no natural circulation is established when main feedwater pumps are stopped. Safety system was designed based on the transient and accident analyses. Turbine driven auxiliary feedwater systems are provided for fast core cooling at LOSP. This reduces the capacity of emergency diesel generators in spite of the high system pressure. Accumulators are required for cooling the tight lattice core at LOCA. Safety of the reactor is evaluated by simplified PSA. The core damage frequency is maintained as the same level of Japanese conventional BWR due to the diversity of feedwater systems in the direct-cycle reactors. 13 refs., 8 figs., 6 tabs." @default.
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- W2467442078 date "1997-12-01" @default.
- W2467442078 modified "2023-09-26" @default.
- W2467442078 title "Safety of a light water cooled reactor operating at supercritical pressure" @default.
- W2467442078 hasPublicationYear "1997" @default.
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