Supporting Thermal Hydraulic Analysis for Small Break LOCA Event Tree of Advanced Integral Water Reactor SMART
SMART (System integrated Modular Advanced ReacTor), which the thermal power is 330 MWth, is under development at the Korea Atomic Energy Research Institute (KAERI). SMART is an integral type pressurized water reactor which contains a pressurizer, reactor coolant pumps (RCPs), and steam generator cassettes(S/Gs) in a single reactor vessel. The response of the primary reactor coolant system (RCS) of SMART to the small break loss of coolant accident (LOCA) is different from the loop type reactors. Plant response of SMART is analyzed by MIDAS/SMR computer code. This code has a model for a helical steam generator which is the type adopted in the SMART reactor. Various combinations of safety systems were analyzed to support the development of event tree for the small break LOCA. When safety injection systems fails to makeup RCS inventory, the operator takes actions to reduce RCS pressure to the shutdown cooling pump shutoff pressure and makes up RCS inventory using the shutdown cooling pumps. This depressurization can be done by opening safety depressurization valve in SMART. The large inventory of primary coolant in SMART enables this action a long time before the core becomes damaged. Based on these calculations, an event tree for the small break LOCA is produced which will be used to estimate the core damage frequency for the SMART reactor.
SMART Small LOCA Integral Reactor Event Tree MIDAS
Youngho Jin Jong-Hwa Park Suhn Choi Seong-Won Cho
Korea Atomic Energy Research Institute 1045 Daedeokdaero, Yuseong-gu, Daejeon, Rep. of KOREA Korea Radiation Technology Institute, Co 34 Gwahakro, Yuseong-gu, Daejeon, Rep. of KOREA
国际会议
上海
英文
2710-2720
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）