Design analysis of core assemblies for supercritical pressure conditions |
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Authors: | X Cheng T Schulenberg D Bittermann P Rau |
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Affiliation: | a Forschungszentrum Karlsruhe, Institute of Nuclear and Energy Technology, Postfach 3640, 76021, Karlsruhe, Germany;b Framatome ANP, Postfach 3220, 91050, Erlangen, Germany |
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Abstract: | The increase of steam parameters to supercritical conditions could reduce the power generating costs of light water reactors significantly Proceedings of SCR-2000 (2000) 1]. Core assemblies, however, will differ from current BWR or PWR design. In this context, this paper summarizes the main results related to a thermal-hydraulic design analysis of applicable fuel assemblies. Starting from a thorough literature survey on heat transfer of supercritical fluids, the current status indicates a large deficiency in the prediction of the heat transfer coefficient under reactor prototypical conditions. For the thermal-hydraulic design of such fuel assemblies the sub-channel analysis code Sub-channel Thermal-hydraulic Analysis in Fuel Assemblies under Supercritical conditions (STAFAS) has been developed, which will have a higher numerical efficiency compared to the conventional sub-channel analysis codes. The effect of several design parameters on the thermal-hydraulic behaviour in sub-channels has been investigated. Based on the results achieved so far, two fuel assembly configurations are recommended for further design analysis, i.e. a tight square lattice and a semi-tight hexagonal lattice. |
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