核电厂传热管破裂后防止蒸汽发生器满溢的研究
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摘要
蒸汽发生器传热管破裂(Steam Generator Tube Rupture, SGTR)事故发生后,反应堆一次侧含有放射性的冷却剂通过传热管破口释放到二次侧,同时,破损的蒸汽发生器(SG)的水位升高,最终满溢,含有放射性的冷却剂将释放到外部环境中。在CPR1000核电厂目前的设计中,发生SGTR事故后,破损的SG都会发生满溢。本文基于目前核电厂的设计,从工艺和控制角度入手,采取相应的改进措施和方法,通过降低高压安注(HHSI)最高注入压头的同时,增加SG高水位停运辅助给水的改进,可以避免SGTR事故后破损蒸汽发生器满溢,使事故过程中没有放射性液体排放到环境中,大大减轻了事故后果。SGTR
After the Steam Generator Tube Rupture(SGTR)accident occurred, the radioactive coolant water on the primary side was released to the secondary side through the break tube of the steam generator(Steam Generator, SG), the water level rises and eventually the damaged SG overflows, and the radioactive coolant water will be released into the environment. In the current design of the CPR1000 nuclear power plant, the damaged SG will overflow after the SGTR accident. Based on the design of the current nuclear power plant, this paper starts with the process and control, and deals with corresponding improvement measures. Finally, the improvement of the High Head Safety Injection(HHSI)and the increase of SG high high water level stop assisted water supply are improved. It can avoid the overflow of the steam generator after the SGTR accident, so that no radioactive liquid is discharged into the environment during the accident, which greatly reduced the consequences of the accident.
After the Steam Generator Tube Rupture(SGTR)accident occurred, the radioactive coolant water on the primary side was released to the secondary side through the break tube of the steam generator(Steam Generator, SG), the water level rises and eventually the damaged SG overflows, and the radioactive coolant water will be released into the environment. In the current design of the CPR1000 nuclear power plant, the damaged SG will overflow after the SGTR accident. Based on the design of the current nuclear power plant, this paper starts with the process and control, and deals with corresponding improvement measures. Finally, the improvement of the High Head Safety Injection(HHSI)and the increase of SG high high water level stop assisted water supply are improved. It can avoid the overflow of the steam generator after the SGTR accident, so that no radioactive liquid is discharged into the environment during the accident, which greatly reduced the consequences of the accident.
引文
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[8]肖三平,叶杰,钱辉,等.AP1000核电厂SGTR事故工况下CMT水位分析[J].核安全,2014,13(3):45-49.
[9]路燕,初起宝,徐宇,等.核动力厂蒸汽发生器模态分析[J].核安全,2018,17(4):37-43.
[10]梅金娜,蔡振,韩姚磊,等.EPRI《蒸汽发生器完整性评估导则》解读[J].核安全,2018,17(1):26-33.
[11]杨舒琦,李兰,谭怡,等.华龙一号SGTR事故源项分析研究[J].核安全,2019,18(2):49-53.
[2]郑华.EPR缓解SGTR事故的设计特点[J].核科学与工程,2010,6(1):15-18.
[3]石俊英.WWER-1000型核电厂SGTR事故分析[J].核动力工程,2002,23(2):51-55.
[4]袁明豪,冯雷,周拥辉,等.AP1000核电厂蒸汽发生器传热管破裂事故的分析研究[J].核安全,2009(4):37-41.
[5]鲍杰,崔军.CPR1000核电厂SGTR事故长期阶段的分析研究[J].核安全,2018,17(4):10-16.
[6]邢继,于沛,李军.华龙一号SGTR事故缓解措施及事故处理[J].核动力工程,2016,37(4):58-63.
[7]李吉根,俞尔俊,戴传曾.秦山核电厂SGTR事故及其处置研究[J].核科学与工程,1996,16(3):193-199.
[8]肖三平,叶杰,钱辉,等.AP1000核电厂SGTR事故工况下CMT水位分析[J].核安全,2014,13(3):45-49.
[9]路燕,初起宝,徐宇,等.核动力厂蒸汽发生器模态分析[J].核安全,2018,17(4):37-43.
[10]梅金娜,蔡振,韩姚磊,等.EPRI《蒸汽发生器完整性评估导则》解读[J].核安全,2018,17(1):26-33.
[11]杨舒琦,李兰,谭怡,等.华龙一号SGTR事故源项分析研究[J].核安全,2019,18(2):49-53.