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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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Stefanini P, Galleni F, Di Piazza I, Pucciarelli A. Liquid-Metal Thermal-Hydraulic Numerical Analyses in Support of the Upcoming CIRCE-THETIS Experimental Campaign. NUCL TECHNOL 2023. [DOI: 10.1080/00295450.2023.2189892] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 03/29/2023]
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Pucciarelli A, Toti A, Castelliti D, Belloni F, Van Tichelen K, Moscardini M, Galleni F, Forgione N. Coupled system thermal Hydraulics/CFD models: General guidelines and applications to heavy liquid metals. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2020.107990] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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STH/CFD coupled calculations of postulated transients from mixed to natural circulation conditions in the NACIE-UP facility. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110913] [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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STH/CFD Coupled Simulation of the Protected Loss of Flow Accident in the CIRCE-HERO Facility. APPLIED SCIENCES-BASEL 2020. [DOI: 10.3390/app10207032] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
Abstract
The paper presents the application of a coupling methodology between Computational Fluid Dynamics (CFD) and System Thermal Hydraulic (STH) codes developed at the University of Pisa. The methodology was applied to the CIRCE-HERO facility in order to reproduce the recently performed experimental conditions simulating a Protected Loss Of Flow Accident (PLOFA). The facility consists of an internal loop, equipped with a fuel pin simulator and a steam generator, and an external pool. In this coupling application, the System code RELAP5 is adopted for the simulation of the internal loop while the CFD code ANSYS Fluent is used for the sake of simulating the pool. The connection between the two addressed domains is provided at the inlet and outlet section of the internal loop; a thermal coupling is also performed in order to reproduce the observed thermal stratification phenomenon. The obtained results are promising and a good agreement was obtained for both the mass flow rates and temperature measurements. Capabilities and limitations of the adopted coupling technique are discussed in the present paper also providing suggestions for improvements and developments to be achieved in the frame of future applications.
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