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CCF analysis of BWR reactor shutdown systems based on the operating experience at the TVO I/II in 1981-1993

机译:根据1981 - 1993年TVO I / II的运行经验,对BWR反应堆停堆系统进行​​CCF分析

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The work constitutes a part of the project conducted within the research program of the Swedish Nuclear Power Inspectorate SKI, aimed to develop the methods and data base for the Common Cause Failure (CCF) analysis of highly redundant reactor scram systems. The data analysis for the TVO I/II plant is focused on the hydraulic scram system, and control rods and drives. It covers operating experiences from 1981 through 1993. (9 refs., 9 figs., 7 tabs.). (Atomindex citation 27:051620)

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