Investigation of flow-regime characteristics in a sloshing pool with mixed-size solid particles-Reference-Cited by-同舟云学术

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Investigation of flow-regime characteristics in a sloshing pool with mixed-size solid particles

Published:2020-05 Issue:5 Volume:52 Page:925-936
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Cheng Songbai,Jin Wenhui,Qin Yitong,Zeng Xiangchu,Wen Junlang

Funder

Science and Technology Planning Project of Guangdong Province

Science and Technology Program of Guangzhou

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference28 articles.

1. Evaluation of Design Measures for Severe Accident Prevention and Consequence Mitigation, ANL-GENIV-128;Tentner,2010

2. Investigation of flow regime in debris bed formation behavior with non-spherical particles;Cheng;Nucl. Eng. Tech.,2018

3. Transient heat transfer characteristics between molten fuel and steel with steel boiling in the CABRI-TPA2 test;Yamano;Nucl. Technol.,2009

4. An assessment of Clinch River breeder reactor core disruptive accident energetics;Theofanous;Nucl. Technol.,1986

5. Investigations of sloshing fluid motions in pools related to recriticalities in liquid-metal fast breeder reactor core melt-down accidents;Maschek;Nucl. Technol.,1992

Cited by 6 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. Experimental investigation on sloshing motion in a liquid pool with binarily mixed-density solid particles;Annals of Nuclear Energy;2022-09

2. Numerical study of gas-injection induced pool sloshing behavior using MPS method;International Journal of Advanced Nuclear Reactor Design and Technology;2022-09

3. Experimental and numerical investigations into molten-pool sloshing motion for severe accident analysis of sodium-cooled fast reactors: A review;Frontiers in Energy Research;2022-08-24

4. Debris Bed Self-Leveling Mechanism and Characteristics for Core Disruptive Accident of Sodium-Cooled Fast Reactor: Review of Experimental and Modeling Investigations;Science and Technology of Nuclear Installations;2022-08-22

5. Knowledge from recent investigations on sloshing motion in a liquid pool with solid particles for severe accident analyses of sodium-cooled fast reactor;Nuclear Engineering and Technology;2022-02

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