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For: Rao Y, Cheng Z, Waddington G. Assessment of ASSERT-PV for prediction of critical heat flux in CANDU bundles. Nuclear Engineering and Design 2014. [DOI: 10.1016/j.nucengdes.2014.06.004] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
Number Cited by Other Article(s)
1
Bromley BP, Cheng Z, Nava Dominguez A, Colton AV. Sensitivity Studies to Assess the Impact of Geometry and Operating/Boundary Condition Perturbations on Thermal-Hydraulic Behavior of Advanced Fuel Channels in Pressure Tube Heavy Water Reactors with Uranium and Thorium-Based Fuels. NUCL TECHNOL 2021. [DOI: 10.1080/00295450.2020.1827658] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
2
Hammouda N, Rao Y. The effect of the advanced drift-flux model of ASSERT-PV on critical heat flux, flow and void distributions in CANDU bundle subchannels. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.02.021] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
3
Assessment of subchannel code ASSERT-PV for supercritical applications. J Supercrit Fluids 2016. [DOI: 10.1016/j.supflu.2016.06.016] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
4
Hammouda N, Cheng Z, Rao YF. A subchannel based annular flow dryout model. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2016.04.002] [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]
5
Assessment of ASSERT-PV for prediction of post-dryout heat transfer in CANDU bundles. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2014.07.031] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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