Preliminary simulation of fuel dispersion in a Lead-Bismuth Eutectic (LBE)-cooled research reactor
作者： Zhen Wang , Gang Wang , Zhixing Gu , Ming Jin , Zhumin Zhao
DOI: 10.1016/J.PNUCENE.2015.07.004
关键词: Nuclear engineering 、 Liquid metal 、 Lead-bismuth eutectic 、 Neutron transport 、 Compaction 、 Porosity 、 Research reactor 、 Materials science 、 Coolant 、 Particle diameter
摘要: Abstract In the severe accident analysis of liquid metal cooled reactors, it is important to understand fuel dispersion behavior which may lead re-criticality and influence on heat removal under core damage conditions. For safety investigation a LBE-cooled research reactor developed by Institute Nuclear Energy Safety Technology (INEST), six cases with different parameters phenomenon in coolant were simulated Neutronics Thermal-hydraulics Coupled simulation program (NTC). Fuel transient results showed that porosity, velocity pattern, particle diameter release position have significant accumulation redistribution. these postulated cases, sweep-out effects dominating processes rather than compaction no took place short term (1000 s). These confirm has certain resistance against accidents re-criticality.
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