Comparative Evaluation of Passive Safety Characteristics of 600, 1,200, and 1,800MWe Burner Reactors
Preliminary safety analyses have been performed to assess the effectiveness of the inherent and passive safety characteristics of burner reactor designs. The proposed design concept is a sodium-cooled, pool-type, and metal-fueled reactor with electricity outputs of 600, 1,200 and 1,800MWe, respectively. The scoping safety analyses focused on quantification of safety margins to cladding failure and sodium boiling in terms of peak transient fuel, cladding, and coolant temperatures during extremely unlikely events. The system transient analysis code SSC-K was used for three ATWS (Anticipated Transient without Scram) events of UTOP, ULOF, and ULOHS. The ATWS initiators encompass all possible reactor accident conditions that might be caused by changes of reactivity, coolant flow, and coolant temperature in the core, respectively. The safety analyses demonstrated that the proposed designs were capable of accommodating the ATWS events without progressing into more severe conditions that might lead to fuel melting, cladding failure, sodium boiling, and loss of core structural integrity. The superior safety characteristics of the metal-fueled core designs made the core shutdown with sufficient margin and the self-regulating core power was achieved by negative reactivity feedbacks in conjunction with large thermal inertia of the primary heat transport system and passive decay heat removal.
Sodium-Cooled Fast Reactor Burner Reactor Passive Safety ATWS
Y. M. Kwon C. H. Cho C. G. Park E. K. Kim H. Song S. J. Kim
Korea Atomic Energy Research Institute 1045 Daedeok St. Yuseong Daejeon, 305-353 Korea
国际会议
上海
英文
2721-2733
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）