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Corzo SF, Ugarte R, Godino DM, Ramajo DE. Loss of flow accident analysis in Atucha II nuclear power plant using RELAP5 model. NUCLEAR ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.nucengdes.2022.112108] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/23/2022]
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Wang X, Kuang B, Hu W, Qiao P, Hou J. Natural circulation with LBE as a working substance to be published in: Progress in nuclear energy. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104428] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/31/2022]
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Simulation of the processes occurring during steam generator tube rupture in the lead cooled reactor unit using HYDRA-IBRAE/LM code. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104278] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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Wu Z, Lu C, Morgan S, Bilbao y Leon S, Bucknor M. A status review on the thermal stratification modeling methods for Sodium-cooled Fast Reactors. PROGRESS IN NUCLEAR ENERGY 2020. [DOI: 10.1016/j.pnucene.2020.103369] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
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Mosunova N, Alipchenkov V, Pribaturin N, Strizhov V, Usov E, Lobanov P, Afremov D, Semchenkov A, Larin I. Lead coolant modeling in system thermal-hydraulic code HYDRA-IBRAE/LM and some validation results. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2019.110463] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Liu W, Wang L, Zhou T, Zhang G, Bai Y. Transient characteristics analysis of lead-based reactor from forced circulation to natural circulation. PROGRESS IN NUCLEAR ENERGY 2019. [DOI: 10.1016/j.pnucene.2019.103052] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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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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Shi L, Bing T, Wang C, Tian W, Qiu S, Wu J, Su G. Experimental investigation of gas lift pump in a lead-bismuth eutectic loop. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.01.042] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
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Experimental studies and computational benchmark on heavy liquid metal natural circulation in a full height-scale test loop for small modular reactors. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.03.001] [Citation(s) in RCA: 7] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/23/2022]
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Xi W, Wang Y, Li X, Huai X, Cai J. Experimental Investigation of the Thermal Hydraulics in Lead Bismuth Eutectic-Helium Experimental Loop of an Accelerator-Driven System. NUCLEAR ENGINEERING AND TECHNOLOGY 2016. [DOI: 10.1016/j.net.2016.04.008] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Natural circulation experiments in a non-uniform diameter lead bismuth loop and validation of LeBENC code. PROGRESS IN NUCLEAR ENERGY 2016. [DOI: 10.1016/j.pnucene.2016.03.005] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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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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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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Bandini G, Polidori M, Gerschenfeld A, Pialla D, Li S, Ma W, Kudinov P, Jeltsov M, Kööp K, Huber K, Cheng X, Bruzzese C, Class A, Prill D, Papukchiev A, Geffray C, Macian-Juan R, Maas L. Assessment of systems codes and their coupling with CFD codes in thermal–hydraulic applications to innovative reactors. NUCLEAR ENGINEERING AND DESIGN 2015. [DOI: 10.1016/j.nucengdes.2014.11.003] [Citation(s) in RCA: 14] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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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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3D numerical simulation of fluid–solid coupled heat transfer with variable property in a LBE-helium heat exchanger. NUCLEAR ENGINEERING AND DESIGN 2014. [DOI: 10.1016/j.nucengdes.2014.04.024] [Citation(s) in RCA: 8] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/19/2022]
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A Computing Approach with the Heat-Loss Model for the Transient Analysis of Liquid Metal Natural Circulation Loop. SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 2014. [DOI: 10.1155/2014/769346] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
Abstract
The transient behaviors of natural circulation loop (NCL) are important for the system reliability under postulated accidents. The heat loss and structure thermal inertia may influence the transient behaviors of NCL greatly, so a transient analysis model with consideration of heat loss was developed based on the MATLAB/Simulink to predict the thermal-hydraulic characteristic of liquid metal NCL. The transient processes including the start-up, the loss of pump, and the shutdown of thermal-hydraulic ADS lead bismuth loop (TALL) experimental facility were simulated by using the model. A good agreement is obtained to validate the transient model. The appended structure would provide significant thermal inertia and flatten the temperature distribution in the transients. The oscillations of temperature and flow rate are also weakened. The temperature difference between hot leg and cold leg would increase with the decrease of heat loss, so the flow rate increases as well. However, a significant increase of hot section temperature may cause a failure of facility integrity due to the decrease of heat loss. Hence, the full power of the core tank may also be limited.
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Natesan K, Velusamy K, Selvaraj P, Chellapandi P, Varatharajan S. Thermal hydraulic investigations of an extended station blackout event in FBTR. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2013.07.022] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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Chen F, Huai X, Cai J, Li X, Meng R. Investigation on the applicability of turbulent-Prandtl-number models for liquid lead-bismuth eutectic. NUCLEAR ENGINEERING AND DESIGN 2013. [DOI: 10.1016/j.nucengdes.2013.01.005] [Citation(s) in RCA: 22] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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Mochizuki H. Plant behavior of a fast breeder reactor under loss of AC power for long period. NUCLEAR ENGINEERING AND DESIGN 2012. [DOI: 10.1016/j.nucengdes.2011.12.031] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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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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