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Su XK, Li XW, Wang XY, Chen QJ, Shi QW, Qiu J, Gu L. Numerical study on conjugate heat transfer characteristics of liquid lead-bismuth eutectic and supercritical carbon dioxide in a PCHE straight channel. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2023.109756] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 02/21/2023]
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Agbevanu KT, Debrah SK, Arthur EM, Shitsi E. Liquid metal cooled fast reactor thermal hydraulic research development: A review. Heliyon 2023; 9:e16580. [PMID: 37287616 PMCID: PMC10241851 DOI: 10.1016/j.heliyon.2023.e16580] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 10/22/2022] [Revised: 05/19/2023] [Accepted: 05/20/2023] [Indexed: 06/09/2023] Open
Abstract
The growing interest in fast reactors demands further innovative technologies to enhance their safety and reliability. Understanding thermal hydraulic activities required for advanced reactor technology in design and development is key. However, knowledge of Heavy Liquid Metal (HLM) coolants technology is not mature. The liquid metal-cooled facilities are required experimental platforms for studying HLM technology. As such, efficient thermal hydraulic experimental result is important in the accurate validation of numerical results. In this vein, there is a need to closely review existing thermo-hydraulic studies in HLM test facilities and the test sections. This review aims to assess existing Lead-cooled Fast Reactor (LFR) research facilities, numerical and validation works and Liquid Metal-cooled Fast Reactor (LMFR) databases around the world in the last two decades. Thus, recent thermal hydraulic research studies on experimental facilities and numerical research that support the design and development of LFRs are discussed. This review paper highlights thermal hydraulic issues and developmental objectives of HLM, briefly describes experimental facilities, experimental campaigns and numerical activities, and identifies research key findings, achievements and future research direction in HLM cooled reactors. This review will enhance knowledge and improve advanced nuclear reactor technology that ensures a sustainable, secure, clean and safe energy future.
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Affiliation(s)
- Kafui Tsoeke Agbevanu
- Department of Nuclear Engineering, School of Nuclear and Allied Sciences, University of Ghana, P.O. Box AE1, Kwabenya, Accra, Ghana
- Department of Computer Science, Ho Technical University, P. O. Box HP 217, Ho, Ghana
| | - Seth Kofi Debrah
- Department of Nuclear Engineering, School of Nuclear and Allied Sciences, University of Ghana, P.O. Box AE1, Kwabenya, Accra, Ghana
- Nuclear Power Institute, Ghana Atomic Energy Commission, P.O. Box LG 80, Legon, Accra, Ghana
| | - Emmanuel Maurice Arthur
- Department of Nuclear Engineering, School of Nuclear and Allied Sciences, University of Ghana, P.O. Box AE1, Kwabenya, Accra, Ghana
- Nuclear Power Institute, Ghana Atomic Energy Commission, P.O. Box LG 80, Legon, Accra, Ghana
| | - Edward Shitsi
- Department of Nuclear Engineering, School of Nuclear and Allied Sciences, University of Ghana, P.O. Box AE1, Kwabenya, Accra, Ghana
- Nuclear Research Centre, National Nuclear Research Institute, Ghana Atomic Energy Commission, P.O. Box LG 80, Legon, Accra, Ghana
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Code development of Single-phase 2-D pressure wave propagation. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109211] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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Rachkov VI, Suslov IR, Khomyakov YS, Shvetsov YE. Analysis of the Consequences of a Large Leak in a Steam Generator in a Two-Circuit Lead-Cooled Reactor Unit. ATOM ENERGY+ 2022. [DOI: 10.1007/s10512-021-00793-w] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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Chen Y, Zhang D, Liang Y, Wang S, Yu Q, Wang C, Tian W, Qiu S, Su G. Preliminary development and validation of ACENA code for heavy liquid metal-gas two phase flow simulation. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108452] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
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Huang X, Chen P, Yin Y, Pang B, Li Y, Gong X, Deng Y. Numerical investigation on LBE-water interaction for heavy liquid metal cooled fast reactors. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110567] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/27/2022]
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Development and verification of the activation analysis code AMY. PROGRESS IN NUCLEAR ENERGY 2018. [DOI: 10.1016/j.pnucene.2018.04.020] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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Wang G. A review of recent numerical and experimental research progress on CDA safety analysis of LBE-/lead-cooled fast reactors. ANN NUCL ENERGY 2017. [DOI: 10.1016/j.anucene.2017.08.049] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.6] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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