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Cong T, Wang J, Gu H. Numerical study on flow-induced vibration of LBE-cooled wire-wrapped rod bundle. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2023.109826] [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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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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Li Y, Meng L, Huang Z, Li S, Wang D, Liu B, Zhang Y, Zhang L, Jiang W. Study on the effects from spacer wires on coolant flow within a CiADS fuel assembly. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2022.109647] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 12/15/2022]
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Transverse mixing characteristics of single-phase flow in the helical cruciform fuel assembly. ANN NUCL ENERGY 2023. [DOI: 10.1016/j.anucene.2022.109427] [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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A novel friction factor model for wire-wrapped rod bundles. NUCLEAR ENGINEERING AND DESIGN 2023. [DOI: 10.1016/j.nucengdes.2022.112104] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/14/2022]
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Pacio J, Van Tichelen K, Eckert S, Wondrak T, Di Piazza I, Lorusso P, Tarantino M, Daubner M, Litfin K, Ariyoshi G, Obayashi H, Sasa T. Advanced Thermal-Hydraulic experiments and instrumentation for heavy liquid metal reactors. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.112010] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/06/2022]
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Cai Q, D'Auria F, Umminger K, Bestion D, Shan J. Prioritizing pressure drop research in nuclear thermal hydraulics. PROGRESS IN NUCLEAR ENERGY 2022. [DOI: 10.1016/j.pnucene.2022.104358] [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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Bovati O, Hassan Y. Implementation of a CFD methodology for computing subchannel friction factors and split parameters in wire-wrapped rod bundles. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111952] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/14/2022]
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Liu M, Wang X, Ni S, Liu L, Gu H. Development of friction factor correlations for hexagonal and square bundles with rough rods based on CFD. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.109163] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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The blockage model of Upgraded Cheng and Todreas correlation for pressure drop in hexagonal wire-wrapped rod bundles. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111874] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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Quan Z, Dix A, Kong R, Kim S, Ishii M, Farmer MT. Pressure Drop in Seven-Pin Wire-Wrapped Rod Bundle for the Sodium Cartridge Loop in Versatile Test Reactor. NUCL SCI ENG 2022. [DOI: 10.1080/00295639.2022.2082232] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/17/2022]
Affiliation(s)
| | - Adam Dix
- Purdue University, West Lafayette, Indiana
| | - Ran Kong
- Purdue University, West Lafayette, Indiana
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Kong R, Kim S, Wahlen R, Pike J, Grimm T. Experiments and CFD simulations of the LBE loop in HYST: A new concept for irradiation experiments in a fast-reactor-like environment. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111774] [Citation(s) in RCA: 2] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Reale Hernandez C, Grishchenko D, Kudinov P, Wallenius J, Luxat J. Development of a CFD-based model to simulate loss of flow transients in a small lead-cooled reactor. NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2022.111773] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/18/2022]
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Dehlin F, Wallenius J, Bortot S. An analytic approach to the design of passively safe lead-cooled reactors. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2022.108971] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/01/2022]
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Liu M, Wang L, Ni S, Wang X, Liu L, Gu H. Experimental investigation on pressure drop of a PWR fuel assembly under low Re conditions. ANN NUCL ENERGY 2022. [DOI: 10.1016/j.anucene.2021.108768] [Citation(s) in RCA: 4] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/01/2022]
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Pacio J, Chen S, Chen Y, Todreas N. Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part I: The Pacio-Chen-Todreas Detailed model (PCTD). NUCLEAR ENGINEERING AND DESIGN 2022. [DOI: 10.1016/j.nucengdes.2021.111607] [Citation(s) in RCA: 2] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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Liu J, Song P, Zhang D, Wang S, Lin C, Liu Y, Zhou L, Wang C, Tian W, Qiu S, Su G, Tian W. Thermal-hydraulic research on rod bundle in the LBE fast reactor with grid spacer. NUCLEAR ENGINEERING AND TECHNOLOGY 2022. [DOI: 10.1016/j.net.2022.01.026] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Numerical investigation of thermal hydraulic behaviors in wire-wrapped bundle with smaller wire diameter of peripheral rods. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108526] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/18/2022]
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Yang BW, Ninokata H, Long J, Liu A, Han B. Subchannel analysis – Current practice and development for the future. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111477] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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Development of a novel two-phase flow solver for nuclear reactor analysis: Validation against sodium boiling experiments. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111422] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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Pacio J, Chen S, Chen Y, Todreas N. Analysis of pressure losses and flow distribution in wire-wrapped hexagonal rod bundles for licensing. Part II: Evaluation of public experimental data. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111606] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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Yang H, Li H, Xue X, Zhou Z. Experimental Investigation of the Friction Factor of Wire-Wrapped Bundles at Low Velocities Under Natural Circulation Flow Conditions. NUCL SCI ENG 2021. [DOI: 10.1080/00295639.2021.1973177] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
Affiliation(s)
- Hongyi Yang
- China Institute of Atomic Energy, Beijing, China
| | - Hongrui Li
- Tsinghua University, Thermal Energy and Power Department, Beijing, China
| | - Xiuli Xue
- China Institute of Atomic Energy, Beijing, China
| | - Zhiwei Zhou
- China Institute of Atomic Energy, Beijing, China
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Kim H, Chen YM, Hassan Y. Prediction of pressure drop in hexagonal wire-wrapped rod bundles using artificial neural network. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111365] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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Merzari E, Cheung FB, Bajorek SM, Hassan Y. 40th Anniversary of the first international topical meeting on nuclear reactor thermal-hydraulics: Highlights of thermal-hydraulics research in the past four decades. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2020.110965] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Song M, Jeong JH, Kim ES. Investigation on subchannel flow distribution in wire-wrapped 37 and 61-pin bundle using computational fluid dynamics. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110904] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/23/2022]
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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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Todreas N, Chen SK, Pacio J. Adventures in study of the pressure losses in wire-wrapped rod bundle arrays. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110910] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Song MS, Jeong JH, Kim ES. Flow visualization on SFR wire-wrapped 19-pin bundle geometry using MIR-PIV-PLIF and comparisons with RANS-based CFD analysis. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2020.107653] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.5] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/24/2022]
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Dovizio D, Mikuž B, Shams A, Roelofs F. Validating RANS to predict the flow behavior in wire-wrapped fuel assemblies. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2019.110376] [Citation(s) in RCA: 8] [Impact Index Per Article: 2.0] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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Hassan Y. High-fidelity experimental measurements for modeling and simulation of nuclear engineering applications. NUCLEAR ENGINEERING AND DESIGN 2019. [DOI: 10.1016/j.nucengdes.2019.110181] [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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Panigrahi PK, Velusamy K. A robust multi phase model to investigate molten material relocation during total flow blockage in SFR fuel subassembly. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2019.05.007] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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