engleski

Application of the coupled code RELAP5- QUABOX/CUBBOX in Best-Estimate Analyses of Nuclear Power Plants

A comprehensive NPP Krško model after steam generator replacement and at uprated conditions (reactor power 1994 MW) with all major control systems for RELAP5/mod3 computer code has been developed. In the paper the results of two operational transients and the Inadvertent depressurization event for both code versions (RELAP5 standalone and coupled code) are presented. The aims of the presented analyses are twofold. First, comparison of point kinetics and 3D neutronic case results can be used for validation of the coupled model, and on the other side to determine the range of applicability of the RELAP5 point kinetics model. Secondly, the RELAP5 models of plant control systems important for operational power changes are verified since the analyzed cases represent the power maneuvering transients.

Nuclear power plant; safety analysis; best estimate methods

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