Abstract
The radial power distribution is uneven in the Pressure Tube type SuperCritical Water-cooled Reactor (PT-SCWR) bundle because of the high fuel enrichment, the separation of light water coolant and heavy water moderator. The uneven profile will usually result in higher cladding temperature which cannot meet the design limit for SCWR. In order to optimize bundle design, the analysis of coupled neutronics/thermal-hydraulics was carried out.The neutronics code WIMS-AECL and the subchannel code ATHAS are selected to conduct the coupled neutronics/thermal-hydraulics analysis for the PT-SCWR 54-elements bundle design. The optimization was carried out through (1) adopting staggered radial uranium enrichment profile and (2) optimizing the pitch-circle radiuses of element rings.The results showed that the obtained optimized bundle can meet the demand of limiting criteria for peak cladding temperature and negative coolant temperature coefficient.
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