PRELIMINARY NO-CORE MELT ASSESSMENT FOR THE HIGH EFFICIENCY CHANNEL PRECONCEPTUAL DESIGN
Several preliminary simulations were performed to assess heat rejection to the moderator from the highefficiency fuel channel for the reference Canadian Supercritical Water-Cooled Reactor in a postulatedloss of coolant accident with loss of emergency core cooling. Utilizing thermal conductivity valuesfor a non-porous zirconia ceramic fuel channel insulator and steady state values between 1% and 5%decay power, simulation results indicated that the sheath temperatures remained below the meltingtemperature for less than ~3% decay heat. Transient calculations were performed for a 76% porousand non-porous zirconia ceramic fuel channel insulator to further quantify accident conditionbehaviour. Areas for further research have been identified.
J.Licht R.Xu
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)