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For: Haque H, Feltes W, Brinkmann G. Thermal response of a modular high temperature reactor during passive cooldown under pressurized and depressurized conditions. Nuclear Engineering and Design 2006. [DOI: 10.1016/j.nucengdes.2005.10.027] [Citation(s) in RCA: 25] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
Number Cited by Other Article(s)
1
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]
2
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]
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
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]
5
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]
6
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]
7
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]
8
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]
9
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]
10
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]
11
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]
12
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]
13
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]
14
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]
15
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]
16
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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