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Analysis on blow-down transient in water ingress accident of high temperature gas-cooled reactor

机译:高温气冷堆进水事故的排污瞬态分析

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Water ingress into the primary circuit is generally recognized as one of the severe accidents with potential hazard to the modular high temperature gas-cooled reactor, which will cause a positive reactivity introduction with the increase of steam density in reactor core to enhance neutron slowing-down, also the chemical corrosion of graphite fuel elements and the damage of reflector structure material. The increase of the primary pressure may result in the opening of the safety valves, consequently leading the release of radioactive isotopes and flammable water gas. The research on water ingress transient is significant for the verification of inherent safety characteristics of high temperature gas-cooled reactor. The 200 MWe high temperature gas-cooled reactor (HTR-PM), designed by the Institute of Nuclear and New Energy Technology of Tsinghua University, is exampled to be analyzed in this paper. The design basis accident (DBA) scenarios of double-ended guillotine break of single heat-exchange tube (steam generator heat-exchange tube rupture) are simulated by the thermal-hydraulic analysis code, and some key concerns which are relative to the amount of water into the reactor core during the blow-down transient are analyzed in detail. The results show that both of water mass and steam ratio of the fluid spouting from the broken heat-exchange tube are affected by break location, which will increase obviously with the broken location closing to the outlet of the heat-exchange tube. The double-ended guillotine rupture at the outlet of the heat-exchange will result more steam penetrates into the reactor core in the design basis accident of water ingress. The mass of water ingress will also be affected by the draining system. It is concluded that, with reasonable optimization on design to balance safety and economy, the total mass of water ingress into the primary circuit of reactor could be limited effectively to meet the safety requirements, and the pollution of radioactive isotoDes releasing to the secondary circuit during the blow-down transient will be prevented.
机译:普遍认为,进入主回路的水是严重的事故之一,可能对模块化高温气冷堆造成潜在危害,随着反应堆堆芯中蒸汽密度的增加,中子减速会引起积极的反应性引入。 ,石墨燃料元件的化学腐蚀和反射镜结构材料的损坏。一次压力的升高可能导致安全阀打开,从而导致放射性同位素和易燃气体的释放。进水瞬态的研究对于验证高温气冷堆固有安全特性具有重要意义。本文以清华大学核能与新能源技术研究所设计的200 MWe高温气冷堆(HTR-PM)为例进行分析。用热工水力分析代码模拟了单根换热管双断头的断头(蒸汽发生器换热管破裂)的设计基准事故(DBA)场景,以及与换热量有关的一些关键问题。详细分析了排污瞬态期间进入反应堆堆芯的水。结果表明,从破裂的换热管喷出的流体的水量和蒸汽比均受破裂位置的影响,破裂位置靠近换热管的出口时,破裂位置会明显增加。在设计基准的进水事故中,热交换出口处的双头断头台断裂将导致更多的蒸汽渗入反应堆堆芯。进水量也将受到排水系统的影响。结论是,通过合理优化设计以平衡安全性和经济性,可以有效限制进入反应堆一次回路的总水量,以满足安全性要求,并且放射性同位素在释放过程中会污染二次回路。吹扫瞬变将被防止。

著录项

  • 来源
    《Nuclear Engineering and Design》 |2014年第5期|404-410|共7页
  • 作者单位

    Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China;

    Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China;

    Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China;

    Institute of Nuclear and New Energy Technology, Tsinghua University, Beijing 100084, China;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
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