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- [12] 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
- [14] Assessment of the thermal load when molten debris interact with a VVER reactor vessel during a severe accident Thermal Engineering (English translation of Teploenergetika), 1996, 43 (03):
- [16] Assessment of thermal load at the stage of interaction between melted korium and the VVER reactor vessel during a severe accident Teploenergetika, 1996, (03): : 9 - 17
- [17] 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 2. Creep deformation and failure of the reactor pressure vessel NUCLEAR ENGINEERING AND DESIGN, 2018, 327 : 161 - 171
- [19] Creep Analysis of Reactor Pressure Vessel Lower Head under Core Meltdown Severe Accident Hedongli Gongcheng/Nuclear Power Engineering, 2019, 40 (02): : 37 - 41