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Relevance of Thermo-Fluid-Dynamics for Establishing the Safety of Nuclear Power Plants

Author(s): D'Auria F.; Cherubini M.; Muellner N.

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Abstract: Accident Management, and related terms ‘procedures’ and ‘strategies’ (instead of Management), constitutes a branch of the nuclear reactor safety. The understanding of the meaning and of the objectives of the AM branch requires the knowledge of the safety/licensing concepts like Design Basis Accident (DBA), Beyond DBA (BDBA), and Severe Accident (SA), as well as Probabilistic Safety Assessment (PSA) and role of Human Factors (HF) within nuclear reactor safety. Based on this terminology, the AM branch occupies a virtual region before or upstream the SA area and aims at forming an additional boundary to the progression of accidents that eventually escaped the DBA boundary. This is done consistently with findings and requirements of the PSA branch, taking into account of the HF and of the available NPP components and systems and of their actual status. The purpose of this paper is to summarize the main findings from the execution of a wide range analysis focused to AM in VVER-1000 (within a European Commission funded Project) with main regard to the qualification of computational tools and the proposal for a optimal AM strategy for this kind of NPP.

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Year: 2007

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