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高温气冷堆换热管断裂事故进水量研究
The study on water ingress mass in the steam generator heat-exchange tube rupture accident of modular high temperature gas-cooled reactor
【Author】 WANG Yan,SHI Lei,LI Fu,ZHENG Yan-hua (Institute of nuclear and new energy technology,Tsinghua University,Beijing 100084,China)
【机构】 清华大学核能与新能源技术研究院;
【摘要】 蒸汽发生器换热管断裂导致一回路进水事故是高温气冷堆所特有的一类重要事故,进水与堆芯石墨化学腐蚀及生成可燃气体可能引起堆内升温、升压,因此是一回路进水是高温气冷堆安全分析十分关注的问题。事故过程中的一回路进水量是决定事故后果严重性的关键因素。本文针对清华大学核能与新能源技术研究院设计的球床模块式高温气冷堆示范工程(HTR-PM),采用热工水力系统分析程序RETRAN-02对单根蒸汽发生器换热管不同位置下的双端(2A)断裂的设计基准进水事故过程进行了研究。分析表明,破口喷放进入一回路的水量与换热管断裂位置有关,泄放系统设计对于事故后一回路进水总量有较大影响。在安全性、经济性等多方面综合考虑下,适当增加泄放管径有助于减少从蒸汽发生器二次侧进入一回路的总进水量。
【Abstract】 The steam generator heat-exchange tube rupture(SGTR) accident is an important and particular accident which will result in water ingress to the primary loop of reactor.Water ingress will result in chemical reaction of graphite fuel and structure with water,which may cause overpressure due to generation of explosive gaseous in large quantity. The study on the water ingress accident is significant for the verification of the inherent characteristics of high temperature gas-cooled reactor.The previous research shows that the amount of water ingress mass is the dominant key factor on the severity of the accident consequence.The 200MWe high temperature gas-cooled reactor(HTR-PM), which is the first modular pebble-bed high temperature gas-cooled reactor in China designed by the Institute of Nuclear and New Energy Technology of Tsinghua University,is selected to be analyzed in this paper.The different DBA accident scenarios of double-ended break of single heat-exchange tube are simulated respectively by the thermal-hydraulic analysis code RETRAN-02.The results show the water ingress mass through the broken heat-exchange tube is related to the break location.The amount of water ingress mass is affected obviously by the capacity of the emptier system.With the balance of safety and economical efficiency,the amount of water ingress mass from the secondary side of steam generator into the primary coolant loop will be reduced by increasing properly the diameter of the draining lines.
【Key words】 HTGR; Water ingress; Heat-exchange tube rupture; Steam generator;
- 【会议录名称】 中国核科学技术进展报告(第二卷)——中国核学会2011年学术年会论文集第3册(核能动力分卷(下))
- 【会议名称】中国核学会2011年学术年会
- 【会议时间】2011-10-11
- 【会议地点】中国贵州贵阳
- 【分类号】TL353.13
- 【主办单位】中国核学会