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For: Kaiser A, Peppler W, Vöröss L. Type of flow, pressure drop, and critical heat flux of a two-phase sodium flow. Nuclear Engineering and Design 1974. [DOI: 10.1016/0029-5493(74)90216-7] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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
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 Ⅰ: Pressure drop characteristics. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2022.109678] [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]
3
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]
4
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]
5
Chenu A, Mikityuk K, Chawla R. Pressure drop modeling and comparisons with experiments for single- and two-phase sodium flow. NUCLEAR ENGINEERING AND DESIGN 2011. [DOI: 10.1016/j.nucengdes.2011.07.009] [Citation(s) in RCA: 21] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
6
Heat transfer during boiling of a liquid metal during emergency cooldown of a fast-neutron reactor. ATOM ENERGY+ 1999. [DOI: 10.1007/bf02673277] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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