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Accident Analysis for Nuclear Power Plants with Graphite Moderated Boiling Water RBMK Reactors

English STI/PUB/1211 92-0-112804-5
59 9 38.00 2005

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Description

Accident analysis is an important tool for confirming the adequacy and efficiency of provisions within the defence in depth concept for the safety of nuclear power plants. In 2002, the IAEA published Safety Reports Series No. 23 on Accident Analysis for Nuclear Power Plants, containing general rules and practical guidance for performing accident analysis applicable to any reactor design. The specific features of individual reactor types are taken into account in separate Safety Reports. The current report provides additional guidance with respect to the specific design features of the graphite moderated boiling water reactors with pressurized channels known as RBMKs. In particular, guidance is provided regarding categorization of initiating events, selection of acceptance criteria, and initial and boundary conditions. Specific suggestions are offered for analysis of different groups of initiating events. The report is intended primarily for analysts coordinating, performing or reviewing computational analyses of transients and accidents for nuclear power plants with RBMKs, on both the utility and regulatory sides.

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