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For: Cheung FB, Baker L. Transient Freezing of Liquids in Tube Flow. NUCL SCI ENG 2017. [DOI: 10.13182/nse76-a26851] [Citation(s) in RCA: 21] [Impact Index Per Article: 3.0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
Number Cited by Other Article(s)
1
Zeng C, Chu X, Liu L, Liu M, Gu H. Performance evaluation of DRACS system of molten salt reactors using a transient solidification model. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2021.111565] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
2
Pandey P, Kulkarni PP, Nayak A, Prasad SV. Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2021. [DOI: 10.1115/1.4046257] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
3
Kazimi MS, Chen JC. A Condensed Review of the Technology of Post-Accident Heat Removal for the Liquid-Metal Fast Breeder Reactor. NUCL TECHNOL 2017. [DOI: 10.13182/nt78-a32033] [Citation(s) in RCA: 8] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
4
Chen R, Oka Y, Li G, Matsuura T. Numerical investigation on melt freezing behavior in a tube by MPS method. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2014.03.049] [Citation(s) in RCA: 30] [Impact Index Per Article: 3.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
5
Molten fuel radial motion and cladding melting during a PCM event in LWRs. NUCLEAR ENGINEERING AND DESIGN 1979. [DOI: 10.1016/0029-5493(79)90179-1] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
6
An assessment of fuel freezing and drainage phenomena in a reactor shield plug following a core disruptive accident. NUCLEAR ENGINEERING AND DESIGN 1978. [DOI: 10.1016/0029-5493(78)90063-8] [Citation(s) in RCA: 18] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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