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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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ECN-RX--97-067 Article (scientific)
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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.-.

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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