A NEUTRON-KINETICS/THERMAL-HYDRAULICS COUPLING METHOD FOR SCWR FUEL ASSEMBLY ANALYSIS
(0) Fuel assembly design is an important R&D activity in the development of an SCWR. For this purpose, a neutron-kinetics/thermal-hydraulics coupling method is established, to analyze the neutron-physical and thermal-hydraulic behaviour of SCWR fuel assembly designs. This coupling method bases on the sub- channel analysis code COBRA-Ⅳ for thermal-hydraulics and the neutron-kinetics code SKETCH-N for neutron- physics. Both the COBRA-Ⅳ code and the SKETCH-N code are accordingly modified. An interface is established for the data transfer between these two codes. This coupling method is applied to an SCWR fuel assembly. The results obtained with the coupling method are compared to results computed without coupling. The results achieved so far emphasize the importance of a coupling approach for the analysis of an SCWR fuel assembly. The coupling method is proven to be well suitable for further applications to SCWR fuel assembly design analysis.
Supercritical water cooled reactor (SCWR) coupling method fuel assembly analysis
Liu, X.J. Yan,Y. Cheng, X.
School of Nuclear Science and Engineering, Shanghai Jiao Tong University Dong chuan Road 800, Shanghai 200240, China
国际会议
上海
英文
216-224
2007-03-12（万方平台首次上网日期，不代表论文的发表时间）