UNCERTAINTIES OF IN-CORE MATERIALS WITH RESPECT TO NUCLEAR DATA FOR THE CANADIAN SCWR
The Canadian supercritical water-cooled reactor (SCWR) is a pressure tube reactor with heavywater moderator. It is intended to operate with a coolant pressure of 25 MPa and temperatures of350?C (inlet) to 625?C (outlet). Other features include PuO2/ThO2 based fuel and advanced fuelbundle and fuel channel designs. In this paper, we present preliminary results from an analysisdetermining sensitivities of k and reactivity calculations of a radially reflected, axially finite freshfuel SCWR to nuclear data, as well as the contribution to calculation uncertainties from nucleardata. This will help determine where improvements are needed in nuclear data for SCWRanalyses.
L.Blomeley J.Pencer
Atomic Energy of Canada Limited,Chalk River,Ontario,Canada
国际会议
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)
西安
英文
1-12
2012-04-18（万方平台首次上网日期，不代表论文的发表时间）