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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]
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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]
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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
Abstract
Multiphase Reactors Engineering and Applications Laboratory performed gas phase dispersion experiments in a separate-effect cold-flow experimental setup for coolant flow within heated channels of the prismatic modular reactor under accident scenario using gaseous tracer technique. The separate-effect experimental setup was designed on light of local velocity measurements obtained by using hot wire anemometry. The measurements consist of pulse-response of gas tracer that is flowing through the mimicked riser channel using air as a carrier. The dispersion of the gas phase within the separate-effect riser channel was described using one-dimensional axial dispersion model. The axial dispersion coefficient and Peclet number of the coolant gas phase and their residence time distribution within were measured. Effect of heating intensities in terms of heat fluxes on the coolant gas dispersion along riser channels were mimicked in the current study by a certain range of volumetric air flow rate ranging from 0.0015 to 0.0034 m3/s which corresponding to heating intensity range from 200 to 1400 W/m2. Results confirm a reduction in the response curve spreads is achieved by increasing the volumetric air velocity (representing heating intensity). Also, the results reveal a reduction in values of axial dispersion coefficient with increasing the air volumetric flow rate.
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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]
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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]
Affiliation(s)
- Ibrahim A. Said
- Chemical and Biochemical Engineering Dept.; Missouri University of Science and Technology; Rolla MO 65409
| | - Mahmoud M. Taha
- Chemical and Biochemical Engineering Dept.; Missouri University of Science and Technology; Rolla MO 65409
| | - Shoaib Usman
- Mining and Nuclear Engineering Dept.; Missouri University of Science and Technology; Rolla MO 65409-0170
| | - Brian G. Woods
- Dept. of Nuclear Engineering and Radiation Health Physics; Oregon State University; Corvallis OR 97331
| | - Muthanna H. Al-Dahhan
- Chemical and Biochemical Engineering Dept.; Missouri University of Science and Technology; Rolla MO 65409
- Mining and Nuclear Engineering Dept.; Missouri University of Science and Technology; Rolla MO 65409-0170
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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]
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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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