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- [8] Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 1. The effect of the inverse melt stratification and in-vessel top cooling of corium pool on the thermal loads acting on VVER-600's reactor pressure vessel during a severe accident NUCLEAR ENGINEERING AND DESIGN, 2018, 326 : 320 - 332
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- [10] External reactor vessel cooling measure in severe accident for pressurized water reactor nuclear power plant Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2009, 43 (01): : 46 - 50