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For: Sorokin AP, Efanov AD, Ivanov EF, Martsinyuk DE, Bogoslovskaya GP, Rymkevich KS, Mal’kov VL. Heat transfer during boiling of a liquid metal during emergency cooldown of a fast-neutron reactor. ATOM ENERGY+ 1999;87:801-7. [DOI: 10.1007/bf02673277] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
Number Cited by Other Article(s)
1
Hou Y, Wang L, Zhang K, Wang M, Wu Y, Tian W, Qiu S, Su G. Experimental study on boiling two-phase of liquid sodium along a 7-rod bundle – Part Ⅱ: Heat transfer characteristics. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2022.109677] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 01/01/2023]
2
Tom S, Mangarjuna Rao P, Venkatraman B, Raghupathy S. Development of CFD based model for sodium flow boiling in narrow channel akin to SFR fuel subchannel towards high void fraction regimes. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111877] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
3
Wu Y, Luo S, Wang L, Hou Y, Su G, Tian W, Qiu S. Review on heat transfer and flow characteristics of liquid sodium (2): Two-phase. PROGRESS IN NUCLEAR ENERGY 2018. [DOI: 10.1016/j.pnucene.2017.11.016] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
4
Experimental Investigations of Heat Transfer Upon Sodium Boiling in a Model Fuel Assembly for Safety Validation of an Advanced Fast Reactor. ATOM ENERGY+ 2016. [DOI: 10.1007/s10512-016-0139-2] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
5
Basic verification of THACS for sodium-cooled fast reactor system analysis. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2014.09.025] [Citation(s) in RCA: 17] [Impact Index Per Article: 1.9] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
6
Hu B, Wu Y, Tian W, Su G, Qiu S. Development of a transient thermal-hydraulic code for analysis of China Demonstration Fast Reactor. ANN NUCL ENERGY 2013. [DOI: 10.1016/j.anucene.2012.12.022] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/27/2022]
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