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Title:
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Afterheat removal from a helium reactor under accident conditions
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Author(s):
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Published by:
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Publication date:
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ECN
NUCLEAIR
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1998
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ECN report number:
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Document type:
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ECN-R--97-015
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Other
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Number of pages:
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Full text:
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43
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Download PDF
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Abstract:
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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