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Study on molten core/coolant interactions during severe accidents of light water reactors

机译：轻水堆严重事故中熔融核/冷却剂相互作用的研究

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Thesis (Ph. D. in Engineering)--University of Tsukuba, (B), no. 1923, 2003.3.25

机译：论文（工程学博士学位）-筑波大学，（B），没有。 1923、2003.3.25

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丸山結; マルヤマユウ;
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年度 2003
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正文语种 ja
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1. 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

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，（IV）使用SEFDAN代码分析TMI-2事故中的堆芯损坏行为
2. 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
3. Thermal-Hydraulics in Uncovered Core of Light Water Reactor in Severe Core Damage Accident, (II)Analysis of Power Burst Facility Severe Fuel Damage Scoping Test with SEFDAN Code [J] . Fumiya TANABE, Ken MURAMATSU, Tohru SUDA Journal of nuclear science and technology . 1986,第10期

机译：发生严重堆芯损坏事故时发现的轻水反应堆堆芯中的热工水力，（II）使用SEFDAN代码对动力爆发设施进行严重燃料损坏范围测试的分析
4. A Visual Study of Molten Metal Fuel Coolant Interactions under an Initial Phase of SFR Severe Accident using Gallium Metal vs Water or R123 [C] . Hyo Heo, Seong Dae Park, Dong Wook Jerng, International topical meeting on nuclear reactor thermal hydraulics . 2015

机译：使用金属镓与水或R123的SFR严重事故初期熔融金属燃料冷却剂相互作用的可视化研究
5. A THEORETICAL STUDY OF ENERGETIC INTERACTIONS BETWEEN HIGH TEMPERATURE MOLTEN MATERIALS AND A LOW TEMPERATURE FLUID (FUEL-COOLANT, INTERACTION, VAPOR EXPLOSION, HEAVY WATER NUCLEAR REACTOR). [D] . CHEN, STEVE HSIU-HUNG. 1984

机译：高温熔融材料与低温流体（燃料，冷却剂，相互作用，蒸气爆炸，重水核反应器）之间的能量相互作用的理论研究。
6. Fukushima-derived radionuclides in sediments of the Japanese Pacific Ocean coast and various Japanese water samples (seawater tap water and coolant water of Fukushima Daiichi reactor unit 5) [O] . Katsumi Shozugawa, Beate Riebe, Clemens Walther, -1

机译：日本太平洋沿岸沉积物和各种日本水样（福岛第一核反应堆5的海水自来水和冷却水）中来自福岛的放射性核素
7. Loss of Coolant Accident (LOCA) / Emergency Core Coolant System (ECCS Evaluation of Risk-Informed Margins Management Strategies for a Representative Pressurized Water Reactor (PWR) [O] . Ronaldo Henriques Szilard 2016

机译：冷却液事故（LOCA）/紧急核心冷却液系统（ECCS对被告知的利润率的评估为代表加压水反应堆（PWR）
8. Effect of Core Melt-Coolant Interactions on Severe Accident Risks in Light-Water Reactors [R] . Evans, N. A. 1983

机译：核心熔体 - 冷却剂相互作用对轻水反应堆严重事故风险的影响

Study on molten core/coolant interactions during severe accidents of light water reactors

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