In-Vessel and Ex-Vessel Corium Stabilization in Light Water Reactor

机译：轻水反应器中的容器和前血管稳定性

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Hwan Yeol Kim; Sevostian Bechta; Jerzy Foit; Seong Wan Hong;
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1. In-Vessel and Ex-Vessel Corium Stabilization in Light Water Reactor [J] . Kim Hwan Yeol, Bechta Sevostian, Foit Jerzy, Science and technology of nuclear installation . 2018,第PTa2期

机译：轻水反应堆中的船内和船外钙稳定
2. Features of heat and deformation behavior of a WER-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 WER-600 's reactor pressure vessel during a severe accident [J] . Loktionov Vladimir, Mukhtarov Erkin, Lyubashevskaya Irina Nuclear Engineering and Design . 2018,第JANa期

机译：在严重事故期间，WER-600反应堆压力容器在皮质池逆分层和恶化的外部容器冷却条件下的热和变形行为特征。第1部分。严重事故期间，反熔分层和皮质池的炉内顶部冷却对WER-600反应堆压力容器上作用的热负荷的影响
3. Measurements of in-vessel and ex-vessel liquid corium surface tension and density in the VITI-MBP test bench within ALISA Euro-Chinese project [J] . Jules DELACROIX, Christophe JOURNEAU, Nourdine CHIKHI, Mechanical Engineering Journal . 2020,第3期

机译：Alisa Euro-Chinese项目中Viti-MBP试验台的血管内和血管液体芯片表面张力和密度的测量
4. Evaluation of In-Vessel Corium Retention through External Reactor Vessel Cooling for Integral Reactor [C] . Rae-Joon Park, Jae Ryong Lee, Sang-Baik Kim, International congress on advances in nuclear power plants . 2012

机译：通过整体反应堆外部反应堆容器冷却来评估容器内钙保留
5. Design and analysis of a nuclear reactor core for innovative small light water reactors. [D] . Soldatov, Alexey I. 2009

机译：设计和分析用于创新型小型轻水反应堆的核反应堆堆芯。
6. Microfluidic reactors for visible-light photocatalytic water purification assisted with thermolysis [O] . Ning Wang, Furui Tan, Li Wan, 2014

机译：用于热解的可见光光催化水净化的微流体反应器
7. Fuel–Coolant Interaction Visualization Test for In-Vessel Corium Retention External Reactor Vessel Cooling (IVR-ERVC) Condition [O] . Young Su Na, Seong-Ho Hong, Jin Ho Song, 2016

机译：燃料 - 冷却剂相互作用可视化测试，用于容器内真空保留外部反应器容器冷却（IVR-ERVC）条件
8. Debris Dispersal in Reactor Material Experiments on Corium-Water Thermal Interactions in Ex-Vessel Geometry [R] . Sienicki, J. J., Spencer, B. W., Squarer, D. 1984

机译：反应堆中的碎片分散材料实验中前体几何中的真皮 - 水热相互作用

In-Vessel and Ex-Vessel Corium Stabilization in Light Water Reactor

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