Structural Integrity Evaluation of a Reactor Cavity during a Steam Explosion for External Reactor Vessel Cooling
نویسندگان
چکیده
Nuclear power is a major source of electricity in the international community. However, significant problem with nuclear that, if severe accident occurs, radiation may leak and cause great damage. As such, research on safety has become increasingly popular worldwide. In this paper, structural integrity reactor cavity during steam explosion—one kind aforementioned accidents—was evaluated. Steam explosions are primarily caused by fuel–coolant interactions (FCI), result from issues cooling system that discharges melt core to outside. A explosion can damage plant, leakage, greatest concern, occur. Chernobyl or Fukushima Daiichi accidents, leakages resulted damages extending beyond country origin. was simulated using values given transient analysis code for explosive reactions (TRACER-II)—the only Korea. The walls were modeled after APR-1400 currently operating concrete, rebars, liner plate evaluated terms stress ductile failure strain limits.
منابع مشابه
Effectiveness of External Reactor Vessel Cooling (ERVC) Strategy for APR1400 and Issues of Phenomenological Uncertainties
متن کامل
Nuclear Reactor Steam Generation
1. Steam Generation 1.1. General Characteristics 1.2. Circulation in Boiling Water Reactors 1.3. Steam Generation in CANDU Reactors 1.4. Steam Generators 1.5. Steam Generator for PWR and CANDU Systems 1.6. Heat Transfer 2. Steam Generator Operation 2.1. Swelling and Shrinking 2.1.1. Steady State Swelling and Shrinking 2.1.2. Transient Swelling and Shrinking 2.2. Level Control 2.3. Carryover 2.4...
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ژورنال
عنوان ژورنال: Energies
سال: 2021
ISSN: ['1996-1073']
DOI: https://doi.org/10.3390/en14123605