NEUTRONICS/HERMALHYDRAULICS COUPLING IN A CANDU SCWR

摘要：

The prediction of the power distribution in a CANDU SCWR requires the implementation of aneutronics/thermalhydaulics coupling approach, due to the dependency between the core powerand thermalhydraulics parameters such as the coolant temperature, the coolant density, and the fueltemperature. Such a coupling can be accomplished in several ways. One approach is to determinethe thermalhydaulics parameters of each channel based on its location in the core, while anotherapproach is to replace them by core-averaged thermalhydaulics parameters, in the radial direction.In this paper, we use the DONJON code to compare both methods. The results show that, for theCANDU SCWR with the 54-element bundle design, the latter approach under-estimates the powerof outer channels, whereas it over-estimates the power of inner ones.

作者: P.Adouki G.Marleau

作者单位: Institut de Genie Nucleaire,Ecole Polytechnique,Montreal,Quebec,Canada

会议类型: 国际会议

会议名称: 3rd China-Canada Joint Workshop on Supercritical Water-Cooled Reactors(第三届中国-加拿大超临界水堆研讨会 (CCSC-2012)

会议地点: 西安

会议语种:英文

页码: 1-10

在线出版日期: 2012-04-18（万方平台首次上网日期，不代表论文的发表时间）