From melt jet break-up to debris bed formation: A review of melt evolution model during fuel-coolant interaction-Reference-Cited by-同舟云学术

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From melt jet break-up to debris bed formation: A review of melt evolution model during fuel-coolant interaction

Published:2022-01 Issue: Volume:165 Page:108642
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Sun Ruiyu,Wu Liangpeng,Ding Wen,Chen Ronghua,Tian Wenxi,Qiu Suizheng,Su G.H.

Funder

National Key Research and Development Program of China

National Natural Science Foundation of China

China Academy of Space Technology

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference177 articles.

1. Vapor explosions;Berthoud;Annu. Rev. Fluid Mech.,2000

2. An assessment of Class-9 (core-melt) accidents for PWR dry-containment systems;Theofanous;Nucl. Eng. Des.,1981

3. Fragmentation mechanisms of a single molten copper jet penetrating a sodium pool—transition from thermal to hydrodynamic fragmentation in instantaneous contact interface temperatures below its freezing point—;Nishimura;J. Nucl. Sci. Technol.,2010

4. Ex-vessel melt-coolant interactions in deep water pool: studies and accident management for Swedish BWRs;Chu;Nucl. Eng. Des.,1995

5. Vapor explosions in light water reactors: A review of theory and modeling;Corradini;Prog. Nucl. Energ.,1988

Cited by 24 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Oxidation of molten zirconium-containing droplet in water;Progress in Nuclear Energy;2024-10

2. Experimental and numerical research on the debris bed formation in severe accidents of nuclear reactors;International Journal of Thermal Sciences;2024-10

3. A numerical study on melt jet breakup in a water pool using coupled VOF and level set method;Nuclear Engineering and Design;2024-09

4. A three-dimensional CFD simulation of corium jet breakup in intensive vapor generation condition;Nuclear Engineering and Technology;2024-07

5. From debris bed formation to self-leveling behaviors in core disruptive accident of sodium-cooled fast reactor;Nuclear Engineering and Design;2024-03

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