Detailed evaluation of safety injection tank effects on in-vessel severe accident progression in a small break LOCA without safety injection

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• 作者：Rae-Joon Park ; ^{rjpark@kaeri.re.kr} ; Kwang-Soon Ha ; Hwan-Yeol Kim ; Jin-Ho Song
• 关键词：Severe accident ; Actuation of safety injection tanks ; Passive coolant injection ; Core melt progression ; Hydrogen generation ; Reactor vessel failure
• 刊名：Annals of Nuclear Energy
• 出版年：2013
• 出版时间：August, 2013
• 年：2013
• 卷：58
• 期：Complete
• 页码：54-59
• 全文大小：820 K

文摘

The effects of coolant injection into a reactor vessel by the passive actuation of SITs (Safety Injection Tanks) on the in-vessel core melt progression under a severe accident have been evaluated in an APR (Advanced Power Reactor) 1400. A best estimate simulation from initiating events of 2-in. and 3-in. break SBLOCAs (Small Break Loss Coolant Accidents) without SI (Safety Injection) to a reactor vessel failure has been carried out using the SCDAP/RELAP5 computer code in conditions with and without the passive actuation of the SITs. The SCDAP/RELAP5 results have shown that the passive coolant injection into the reactor vessel by the actuation of the SITs leads to postpone the reactor vessel failure time by 4-5 h in the SBLOCA without SI. At the time of the reactor vessel failure, 44.5 % and 42.8 % of the fuel rod cladding were oxidized in the 2-in. and 3-in. SBLOCAs with the actuation of the SITs, respectively. However, 37.5 % and 34.6 % of the fuel rod cladding were oxidized in the 2-in. and the 3-in. SBLOCAs without the actuation of the SITs, respectively. Even though the SITs are designed for a large break LOCA, their actuation is very effective on the delay of a reactor vessel failure in spite of more hydrogen generation in the SBLOCA without SI.