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首页> 外文会议>8th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation and Safety. >Thermal-hydraulic researches of safety problems in fast breeder reactors
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Thermal-hydraulic researches of safety problems in fast breeder reactors

机译：快速增殖反应堆安全问题的热工水力研究

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摘要

The researches on thermophysical validation of nuclear facility safety as applied to fast reactor with sodium cooling are performed for a wide range of problems including the thermohydraulics of reactor core and individual subassemblies, transient processes with mixed and natural convection of the coolant within reactor vessel, as well as in the individual subassemblies, processes in the upper chamber including interaction of coolant jets above subassembly heads, temperature pulsations in the coolant and in structure elements, gas capture from sodium surface in reactor gas volume and its transport along facility piping, influencing of blockage of a part of a flow area subassembly, processes of heat and mass transfer connected with generation, transport, deposition and accumulation of impurities in sodium loops and protective gas in fast reactor facilities, vibration stability in structure elements, onset and development of sodium boiling, sodium-water interaction, sodium fires in case of loss of pressure in circulation loops and generation of aerosols, corium-sodium interaction in case of fuel melting during heavy accident and steam explosion.
机译：针对带有钠冷却的快速反应堆的核设施安全的热物理验证研究进行了广泛的研究，包括反应堆堆芯和单个子组件的热工水力，反应堆容器内冷却剂混合自然对流的过渡过程，以及以及在各个子组件中，上部腔室中的过程包括子组件头部上方的冷却液射流的相互作用，冷却剂中和结构元件中的温度脉动，反应器气体量中钠表面的气体捕集及其沿设施管道的运输，对堵塞的影响流动部分组件的一部分，热和质量传递过程与快速反应堆设施中钠回路和保护性气体中杂质的产生，运输，沉积和积累，结构元素的振动稳定性，钠沸腾的发生和发展有关，钠与水的相互作用，以防钠起火重大事故和蒸汽爆炸中的燃料熔化时，循环回路中的压力损失和气溶胶的生成，钙钠相互作用的问题。

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