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Afterheat removal from a helium reactor under accident conditions
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ECN-R--97-015 Overig
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The IAEA Co-ordinated Research Programme (CRP) on 'Heat Transport andAfterheat Removal for Gas Cooled Reactors under Accident Conditions' has organised benchmark analyses to support verification and validation of analytical tools used by the participants to predict the thermal behaviour of advanced gas cooled reactors during accidents. One of these benchmark analyses concerns the code-to-code analysis of the Gas Turbine Modular Helium Reactor (GT-MHR) plutonium burner accidents. This report describes the heat transport inside the reactor core to the Reactor Cavity Cooling System (RCCS). For this purpose, the heat transfer mechanisms as well as the flow patterns inside the core, the reactor pressure vessel, and the cavity have been calculated by the Computational Fluid Dynamics (CFD) code CFX-F3D. The behaviour of the RCCS itself is not described. One calculation considers the full power operation, while two calculations consider Loss Of Forced Convection (LOFC) accidents, one at pressurised conditions and the other at depressurised conditions. 6 refs.

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