An initial appraisal of the event-tree methodology used in the Angra 1 nuclear power station probabilistic safety assessment

P.F. Frutuoso e Melo, J.E. Lima, L.F. Oliveira
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Abstract

The event-tree analyses of the Angra 1 nuclear power plant probabilistic safety assessment were performed by means of the explicit method of event-tree modelling of shared-equipment dependencies, from which some insights were drawn. At first, we discuss in this paper the effects of collapsing equal impact vectors (from the quantification point of view also). The second feature discussed is related to a critical analysis of the dependency matrix concept in view of a counterpart to it—namely, the GO methodology in the context of modelling intersystem dependencies. Finally, we discuss the possibility of using our computerized event-tree analysis methodology for assessing the unavailability of the involved standby safety systems, most of which are recognized to be noncoherent structures.

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安格拉1号核电站概率安全评价中使用的事件树方法的初步评价
采用共享设备依赖关系事件树建模的显式方法,对安格拉1号核电站概率安全评估进行了事件树分析,并从中得到一些启示。首先,我们从量化的角度讨论了等冲击向量坍缩的影响。讨论的第二个特征与依赖矩阵概念的关键分析有关,即在建模系统间依赖关系的背景下使用GO方法。最后,我们讨论了使用我们的计算机化事件树分析方法来评估所涉及的备用安全系统不可用性的可能性,其中大多数被认为是非相干结构。
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APPENDIX C: OPTIMUM ARRANGEMENT OF COMPONENTS IN CONSECUTIVE‐2‐OUT‐OF‐ N : F SYSTEMS APPENDIX A: GAMMA TABLE APPENDIX H: COMPUTER LISTING OF THE NEWTON–RAPHSON METHOD APPENDIX B: COMPUTER PROGRAM TO CALCULATE THE RELIABILITY OF A CONSECUTIVE‐ k ‐OUT‐OF‐ n : F SYSTEM SYSTEM RELIABILITY EVALUATION
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