An Evaluation of RCS Depressurization before Reactor Vessel Failure by using SCDAP/RELAP5
A potential depressurization of the reactor coolant system (RCS) before a reactor vessel failure during a high pressure severe accident sequence has been evaluated for the consideration of containment bypass and direct containment heating (DCH) by high pressure melt ejection (HPME). A total loss of feed water (TLOFW) and a station blackout (SBO) of the advanced power reactor 1400 (APR1400) has been evaluated from an initiating event to a creep failure of the RCS boundary by using the SCDAP/RELAP5 computer code. In addition, the intentional depressurization of the RCS by using power operated safety relief valves (POSRVs) has been evaluated. The SCDAPRELAP5 results have shown that the pressurizer surge line failed before the reactor vessel failure, but the steam generator U tubes did not fail. The intentional depressurization of the RCS by using POSRV was effective for DCH prevention in the event of a reactor vessel failure.
Severe Accident Melt Progression RCS Depressurization Creep Rupture Vessel Failure
Rae-Joon Park Kyung-Ho Kang Seong-Wan Hong
Korea Atomic Energy Research Institute 1045 Daedeok-daero, Yuseong-gu, Daejeon, Korea
国际会议
上海
英文
400-412
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）