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Title:
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Results of the GT-MHR benchmark with the CFX code: 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-RX--97-067
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Article (scientific)
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Number of pages:
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25
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Published in: To be published in an IEA Tecdoc on 'Heat transport and afterheat removal for gas cooled reactors under accident conditions' (), , , Vol., p.-.
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 section 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. CFX-F3D flow modelling software performs
Computational Fluid Dynamics (CFD) calculations. This code has been developed
by AEA Technology and solves (partial differential) conservation equations
for mass, momentum (Navier-Stokes equations) and energy together with
their-boundary conditions. For this purpose, the software uses the finite
volume method to discretise these equations. The radiative heat transfer is
taken into account. CFX-F3D has-been run on a Silicon Graphics Power
Challenge workstation. 8 refs.
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