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For: Tung YH, Ferng YM, Johnson RW, Chieng CC. Transient LOFA computations for a VHTR using one-twelfth core flow models. Nuclear Engineering and Design 2016. [DOI: 10.1016/j.nucengdes.2016.03.002] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
Number Cited by Other Article(s)
1
Podila K, Chen Q, Huang X, Li C, Rao Y, Waddington G, Jafri T. Coupled simulations for prismatic gas-cooled reactor. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111858] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
2
Colombo M, Fairweather M. Study of nuclear reactor external vessel passive cooling using computational fluid dynamics. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111186] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
3
Said I, Usman S, Al-Dahhan M, Moharam M, Alexander V. Axial dispersion and mixing of coolant gas within a separate-effect prismatic modular reactor. NUCLEAR ENERGY AND TECHNOLOGY 2018. [DOI: 10.3897/nucet.4.27346] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]  Open
4
Takamatsu K. Thermal-hydraulic analyses of the High-Temperature engineering Test Reactor for loss of forced cooling at 30% reactor power. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.03.032] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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