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For: Tung YH, Johnson RW, Ferng YM, Chieng CC. Modeling strategies to compute natural circulation using CFD in a VHTR after a LOFA. Nuclear Engineering and Design 2014. [DOI: 10.1016/j.nucengdes.2014.04.012] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
Number Cited by Other Article(s)
1
Hedayat A, Davari A. Feasibility study to increase the reactor power at natural convection mode in Tehran Research Reactor (TRR) through a hybrid thermal-hydraulic simulation and analysis using the RELAP5 code and Computational Fluid Dynamic (CFD) modeling by ANSYS-FLUENT. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104285] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
2
Wang C, Liu Y, Sun X, Sabharwall P. A hybrid porous model for full reactor core scale CFD investigation of a prismatic HTGR. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2020.107916] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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
Assessment of RELAP5 matrix solvers for a two-phase natural circulation loop. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.03.023] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
5
Investigation of the Thermal Performance of a Vertical Two-Phase Closed Thermosyphon as a Passive Cooling System for a Nuclear Reactor Spent Fuel Storage Pool. NUCLEAR ENGINEERING AND TECHNOLOGY 2017. [DOI: 10.1016/j.net.2016.10.008] [Citation(s) in RCA: 34] [Impact Index Per Article: 4.9] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
6
Said IA, Taha MM, Usman S, Woods BG, Al-Dahhan MH. Investigation of natural convection heat transfer in a unique scaled-down dual-channel facility. AIChE J 2016. [DOI: 10.1002/aic.15583] [Citation(s) in RCA: 13] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/07/2022]
7
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] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
8
Prediction of Missouri S&T Reactor's natural convection with porous media approximation. NUCLEAR ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.nucengdes.2015.01.001] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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