2-D AND 3-D EVALUATION OF NEUTRONIC PROPERTIES ALONG A CANADIAN SCWR FUEL CHANNEL

摘要：

In this study a 2-D and 3-D evaluation of two groups cell averaged cross sections and integratedflux along a Canadian SCWR fuel channel under normal operating conditions has been realized.With the SERPENT code, two models have been developed: (1) a complete 3-D fuel channel thattakes into account temperature and density profiles along the fuel channel in a single model, (2) aseries of 2-D calculations performed at different position along the fuel channel with distinct setsof temperatures and densities. This preliminary study demonstrates that, from the neutronicpoint of view, the axial coupling along the fuel channel appears to be low compared to the effectsof the reflector and of the boundary conditions.

作者: G.Harrisson G.Marleau

作者单位: Institute of Nuclear Engineering cole Polytechnique de Montréal

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: 1-9

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）