Feasibility Analysis of Representative Configurations of Core Degradation Situation During Severe Accidents in Nuclear Reactors

Marat Margulis; Erez Gilad; Patrick Blaise

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Feasibility Analysis of Representative Configurations of Core Degradation Situation During Severe Accidents in Nuclear Reactors

机译：核反应堆严重事故中堆芯退化情况典型配置的可行性分析

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《Nuclear Energy》 |2020年第3期|44-45|共2页
作者
Marat Margulis; Erez Gilad; Patrick Blaise;
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The Unit of Nuclear Engineering Ben-Gurion University of the Negev Israel SPESI/LP2E CEA Cadarache France;

The Unit of Nuclear Engineering Ben-Gurion University of the Negev Israel;

SPESI/LP2E CEA Cadarache France;

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1. Design Analysis of the Molten Core Confinement within the Reactor Vessel in the Case of Severe Accidents at Nuclear Power Plants Equipped with a Reactor of the VVER Type [J] . Yu. A. Zvonaryov, M. A. Budaev, A. M. Volchek, Physics of atomic nuclei . 2013,第14期

机译：在装有VVER型反应堆的核电厂发生严重事故的情况下，反应堆容器内熔核限制区的设计分析
2. Thermal-Hydraulics in Uncovered Core of Light Water Reactor in Severe Core Damage Accident, (IV)Analysis of Core Damage Behavior in TMI-2 Accident with SEFDAN Code [J] . Fumiya TANABE, Tohru SUDA Journal of nuclear science and technology . 1987,第1期

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3. Thermal-Hydraulics in Uncovered Core of Light Water Reactor in Severe Core Damage Accident, (III)Analysis of Power Burst Facility Severe Fuel Damage 1-1 Test with SEFDAN Code [J] . Ken MURAMATSU, Fumiya TANABE, Tohru SUDA Journal of nuclear science and technology . 1986,第11期

机译：严重堆芯损坏事故中轻水反应堆裸露堆芯的热工液压，（III）电力爆炸装置分析严重燃料损坏1-1用SEFDAN代码进行测试
4. RECENT EXPERIMENTS AND NUMERICAL SIMULATIONS ON COOLABILITY OF DEGRADED CORES IN THE LATE PHASE OF SEVERE ACCIDENTS OF LIGHT WATER REACTORS [C] . J. Starflinger, M. Buck, R. Kulenovic, Pacific basin nuclear conference . 2014

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5. Investigation of the Coupled Nuclear, Thermal-Hydraulic, and Thermomechanical Response of a Natural Circulation Research Reactor Under Severe Reactivity-Initiated Accident Transients [D] . Talley, Darren Glenn. 2019

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6. Assessment of environmental radioactive surface contamination from a hypothetical nuclear research reactor accident [O] . Ned Xoubi 2020

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7. Code assessment and modelling for Design Basis Accident analysis of the European Sodium Fast Reactor design. Part II: Optimised core and representative transients analysis [O] . Lázaro Núñez Álvaro, Schikorr M, Mikityuk K., 2014

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8. MATADOR (Methods for the Analysis of Transport and Deposition of Radionuclides): A Computer Code for the Analysis of Radionuclide Behavior during Degraded Core Accidents in Light Water Reactors. [R] . Baybutt, P., Raghuram, S., Avci, H. I. 1985

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Feasibility Analysis of Representative Configurations of Core Degradation Situation During Severe Accidents in Nuclear Reactors

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