ESTIMATION OF CONCEPTUAL SUPERCRITICAL WATER REACTOR RESPONSE TO A SMALL LOSS OF COOLANT ACCIDENT
The proposed supercritical water based GEN-Ⅳ fuel channel nuclear reactor design will employ temperatures and pressures well beyond the operating conditions of current reactor designs. These fluid conditions and their impact on components must be assessed for nuclear safety implications including differences in design basis requirements, differences in the progression of postulated accidents and safety system trip parameter adequacy. Specifically, temperatures and pressures involved in such a design, on the order of 500℃ and 24MPa, are significantly higher than any previously considered in safety analysis of current reactor designs. This paper presents the progress and status in the development of models for use in safety analysis simulations of a conceptual Supercritical Water Reactor (SCWR) design. Due to the preliminary nature of the R & D activities and status of supercritical models, Best Estimate and Uncertainty (BEAU) methods are aptly suited for analysis of conceptual designs because they explicitly treat uncertainty in key parameters. Preliminary results and the sensitivity to certain key input assumptions are presented for the initial stages of a BEAU evaluation of a small loss of coolant accident in a SCWR.
Novog, D.R. Luxat, J. Leung, L.K.H.
McMaster University, Hamilton, Ontario, Canada Atomic Energy of Canada Limited, Chalk River, Ontario, Canada
国际会议
上海
英文
108-117
2007-03-12（万方平台首次上网日期，不代表论文的发表时间）