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Aging Study of Boiling Water Reactor Residual Heat Removal System.

机译:沸水反应器余热排出系统的老化研究。

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A study of the aging effects on Residual Heat Removal (RHR) systems in Boiling Water Reactors (BWRs) was performed as part of the Nuclear Plant Aging Research (NPAR) program. The objectives of the NPAR program are to provide a technical basis for the identification and evaluation of degradation caused by age in nuclear power plant applications. The information from this and other NPAR studies will be used to assess the impact of aging on plant safety and to develop effective mitigating actions. A computer program (PRAAGE-1988) was developed and implemented to model a typical RHR design and perform time-dependent Probabilistic Risk Assessment (PRA) calculations. Time-dependent failure probabilities were input to the PRAAGE program to evaluate the effects of aging on component importance and system unavailability.

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