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Shi L, Su G, Zhu F, Bing T, Hou Y, Wei S, Wang C, Tian W, Qiu S, Wu J. Experimental study on the natural circulation capability and heat transfer characteristic of liquid lead bismuth eutectic. PROGRESS IN NUCLEAR ENERGY 2019. [DOI: 10.1016/j.pnucene.2019.03.003] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Zuo J, Tian W, Qiu S, Su G. Transient safety analysis for simplified accelerator driven system with gas-lift pump. PROGRESS IN NUCLEAR ENERGY 2018. [DOI: 10.1016/j.pnucene.2018.01.003] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Borgohain A, Srivastava A, Jana S, Maheshwari N, Kulkarni R, Vijayan P, Tewari R, Ram AM, Jha S. Natural circulation studies in a LBE loop for a wide range of temperature. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2016.01.029] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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CFD Analysis of the Primary Cooling System for the Small Modular Natural Circulation Lead Cooled Fast Reactor SNRLFR-100. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2016. [DOI: 10.1155/2016/9612120] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
Abstract
Small modular reactor (SMR) has drawn wide attention in the past decades, and Lead cooled fast reactor (LFR) is one of the most promising advanced reactors which are able to meet the safety economic goals of Gen-IV nuclear energy systems. A small modular natural circulation lead cooled fast reactor-100 MWth (SNRLFR-100) is being developed by University of Science and Technology of China (USTC). In the present work, a 3D CFD model, primary heat exchanger model, fuel pin model, and point kinetic model were established based on some reasonable simplifications and assumptions, the steady-state natural circulation characteristics of SNCLFR-100 primary cooling system were discussed and illustrated, and some reasonable suggestions were proposed for the reactor’s thermal-hydraulic and structural design. Moreover, in order to have a first evaluation of the system behavior in accident conditions, an unprotected loss of heat sink (ULOHS) transient simulation at beginning of the reactor cycle (BOC) has been analyzed and discussed based on the steady-state simulation results. The key temperatures of the reactor core are all under the safety limits at transient state; the reactor has excellent thermal-hydraulic performance.
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Zhao P, Li S, Chen Z, Zheng J, Chen H. Natural circulation characteristics analysis of a small modular natural circulation lead–bismuth eutectic cooled fast reactor. PROGRESS IN NUCLEAR ENERGY 2015. [DOI: 10.1016/j.pnucene.2015.03.013] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Li Y, Lv K, Chen L, Gao S, Huang Q. Experiments and analysis on LBE steady natural circulation in a rectangular shape loop. PROGRESS IN NUCLEAR ENERGY 2015. [DOI: 10.1016/j.pnucene.2014.12.009] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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Basu DN, Bhattacharyya S, Das P. A review of modern advances in analyses and applications of single-phase natural circulation loop in nuclear thermal hydraulics. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2014.09.011] [Citation(s) in RCA: 68] [Impact Index Per Article: 6.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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Ma W, Karbojian A, Sehgal BR, Dinh TN. Thermal-hydraulic performance of heavy liquid metal in straight-tube and U-tube heat exchangers. NUCLEAR ENGINEERING AND DESIGN 2009. [DOI: 10.1016/j.nucengdes.2009.03.014] [Citation(s) in RCA: 21] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Experimental study on natural circulation and its stability in a heavy liquid metal loop. NUCLEAR ENGINEERING AND DESIGN 2007. [DOI: 10.1016/j.nucengdes.2007.02.023] [Citation(s) in RCA: 37] [Impact Index Per Article: 2.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/30/2022]
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Ma W, Bubelis E, Karbojian A, Sehgal BR, Coddington P. Transient experiments from the thermal-hydraulic ADS lead bismuth loop (TALL) and comparative TRAC/AAA analysis. NUCLEAR ENGINEERING AND DESIGN 2006. [DOI: 10.1016/j.nucengdes.2006.01.006] [Citation(s) in RCA: 33] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Computational fluid dynamics analysis of spallation target for experimental accelerator-driven transmutation system. NUCLEAR ENGINEERING AND DESIGN 2005. [DOI: 10.1016/j.nucengdes.2004.11.007] [Citation(s) in RCA: 13] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/21/2022]
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Feynman-α measurements on the fast critical zero-power reactor masurca. PROGRESS IN NUCLEAR ENERGY 2005. [DOI: 10.1016/j.pnucene.2005.01.002] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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