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Akbayir O. Numerical analysis of alternative operating temperatures on a modular helium reactor under accident conditions. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111472] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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2
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Rudra AV, Kalaga DV, Kawaji M. Experimental Investigation of Natural Circulation During Air-Ingress Scenario in a Very High Temperature Reactor. NUCL SCI ENG 2019. [DOI: 10.1080/00295639.2019.1595311] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
Affiliation(s)
- Apoorva V. Rudra
- City College of New York, CUNY, Chemical Engineering Department, New York, New York 10031
| | - Dinesh V. Kalaga
- City College of New York, CUNY, Chemical Engineering Department, New York, New York 10031
- City College of New York, CUNY, Mechanical Engineering Department, New York, New York 10031
| | - Masahiro Kawaji
- City College of New York, CUNY, Mechanical Engineering Department, New York, New York 10031
- City College of New York, CUNY, The Energy Institute, New York, New York 10031
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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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Gou F, Chen F, Dong Y. Preliminary phenomena identification and ranking tables on the subject of the High Temperature Gas-cooled Reactor-Pebble Bed Module thermal fluids and accident analysis. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.03.022] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
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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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Three Design Basis Accidents’ Analysis on the HTR-10GT. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2017. [DOI: 10.1155/2017/1686291] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
Abstract
The study simulated the design basis accidents (DBAs) sequences of the HTR-10GT core with THERMIX. When a DBA happens, the protection system will receive a scram signal which shall lead to active measures to shut down the reactor following it. In the paper, three typical DBA cases were studied. They include an accident induced by station blackout, a case caused by the withdrawal of one control rod out of the core by a mistake, and a case resulting from an earthquake, respectively. The simulation results illustrate that the fuel peak temperatures in the core during these accidents are 1066°C, 1201°C and 1067°C, respectively. It is shown that the HTR-10GT has a good safety characteristic.
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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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9
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McVay KL, Park JH, Lee S, Hassan YA, Anand N. Preliminary tests of particle image velocimetry for the upper plenum of a scaled model of a very high temperature gas cooled reactor. PROGRESS IN NUCLEAR ENERGY 2015. [DOI: 10.1016/j.pnucene.2015.04.004] [Citation(s) in RCA: 9] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Porous media approach in thermohydraulic analysis of high temperature reactors in pressurized/depressurized cooldown: An improvement. PROGRESS IN NUCLEAR ENERGY 2015. [DOI: 10.1016/j.pnucene.2014.11.017] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/13/2022]
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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] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Trinuruk P, Obara T. Concept of prismatic high temperature gas-cooled reactor with SiC coating on graphite structures. ANN NUCL ENERGY 2014. [DOI: 10.1016/j.anucene.2013.08.019] [Citation(s) in RCA: 8] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/26/2022]
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13
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Study of natural circulation in a VHTR after a LOFA using different turbulence models. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2013.04.009] [Citation(s) in RCA: 19] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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Freis D, Bottomley P, Kellerbauer A, Rondinella V, Van Uffelen P. Accident testing of high-temperature reactor fuel elements from the HFR-EU1bis irradiation. NUCLEAR ENGINEERING AND DESIGN 2011. [DOI: 10.1016/j.nucengdes.2011.05.026] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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CHEN F, DONG Y, ZHENG Y, SHI L, ZHANG Z. Benchmark Calculation for the Steady-State Temperature Distribution of the HTR-10 under Full-Power Operation. J NUCL SCI TECHNOL 2009. [DOI: 10.1080/18811248.2007.9711564] [Citation(s) in RCA: 8] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/28/2022]
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Post-test analysis of helium circulator trip without scram at 3MW power level on the HTR-10. NUCLEAR ENGINEERING AND DESIGN 2009. [DOI: 10.1016/j.nucengdes.2009.02.009] [Citation(s) in RCA: 8] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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