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Keywords: LFR
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Proceedings Papers

Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation

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Shuowang Fan, Yutong Chen, Dalin Zhang, Xiaoli Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A045, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134796
https://doi.org/10.1115/ICONE31-134796
... (LFR) is an important candidate reactor for the Generation-IV nuclear energy systems, where the Molten Fuel-Coolant Interaction (MFCI) process differs from that occurred in light water reactors and sodium cooled fast reactors due to the coolant property differences. In the lack of experimental...
View Paper titled, Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation
Open the PDF for Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation in another window
Topics: Fast neutron reactors, Stainless steel, Coolants, Temperature, Accidents, Pressure, Safety, Sodium, Temperature distribution, Vessels
Proceedings Papers

Research on the Applicability of the IWF Model to Coupled Heat Transfer Between Intra- and Inter-Assembly in LFR

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Di Wu, Minyang Gui, Jie Cheng, Jianjun Wang
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A007, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-131238
https://doi.org/10.1115/ICONE31-131238
...Proceedings of the 2024 31st International Conference on Nuclear Engineering ICONE31 August 4-8, 2024, Prague, Czech Republic ICONE31-131238 RESEARCH ON THE APPLICABILITY OF THE IWF MODEL TO COUPLED HEAT TRANSFER BETWEEN INTRA- AND INTER-ASSEMBLY IN LFR Di Wu College of Nuclear Science...
View Paper titled, Research on the Applicability of the IWF Model to Coupled Heat Transfer Between Intra- and Inter-Assembly in LFR
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Topics: Heat transfer, Manufacturing, Numerical analysis, Safety, Flow (Dynamics), Fluids, Accuracy and precision, Boundary-value problems, Design, Energy generation
Proceedings Papers

SIMMER-III Code Simulation of High-Pressure Water-Lead Interaction in Westinghouse’s LEWIN Test Facility

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Alessandro Bellomo, Mattia Massone, Simone Gianfelici, Fabio Martini, Sung Jin Lee, Mariano Tarantino, Francesco Galleni, Andrea Pucciarelli, Alessio Pesetti
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136222
https://doi.org/10.1115/ICONE31-136222
... Abstract The Lead-cooled Fast Reactor (LFR) is one of the six advanced reactor system types selected in the Generation-IV (Gen IV) program. Westinghouse (WEC) is developing a highly simplified, passively safe, medium-size, economic Gen-IV LFR as its next-generation utility-scale nuclear power...
View Paper titled, SIMMER-III Code Simulation of High-Pressure Water-Lead Interaction in Westinghouse’s LEWIN Test Facility
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Topics: Coolants, High pressure (Physics), Simulation, Test facilities, Water
Proceedings Papers

Study on Bubble Migration Characteristics in a Lead-Cooled Fast Reactor After Steam Generator Tube Rupture Accident

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Zhenyu Feng, Dalin Zhang, Haoyu Jiao, Yutong Chen, Yue Lin, Wenxi Tian, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A062, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135457
https://doi.org/10.1115/ICONE31-135457
... Abstract In this paper, the bubble migration characteristics of LFR after SGTR accidents are investigated based on the DPM. Firstly, the geometric and mesh models of the primary coolant system of the LFR are established, and the drag coefficient model of bubbles in the DPM is validated based...
View Paper titled, Study on Bubble Migration Characteristics in a Lead-Cooled Fast Reactor After Steam Generator Tube Rupture Accident
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Topics: Accidents, Boilers, Bubbles, Fast neutron reactors, Rupture
Proceedings Papers

Optimization of Core Parameters Based on Artificial Neural Network Surrogate Model

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Shu Chen, Peng Ding, Shuowen Hu, Wenqing Xia, Min Liu, Fengwan Yu, Wenhuai Li
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A005, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90511
https://doi.org/10.1115/ICONE29-90511
... constructed and regulated, and be a more efficient simulators in a innovate reactor optimization. The above work is completed in Sinan Platform, a multidisciplinary intelligent design platform developed by China Nuclear Power Technology Research Institute Co. Ltd. Keywords: LFR, neural network, surrogate...
View Paper titled, Optimization of Core Parameters Based on Artificial Neural Network Surrogate Model
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Topics: Artificial neural networks, Optimization
Proceedings Papers

Numerical Study on Heat Transfer Enhancement of Modified Wall in U-Tube Steam Generator in LFR

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Junjie Yuan, Li Liu
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A049, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91701
https://doi.org/10.1115/ICONE29-91701
... Abstract As the heat exchange device of the primary and secondary circuits in the lead-bismuth fast reactor (LFR), the steam generator needs to consider its heat exchange performance and safety. To achieve a better heat transfer effect and reduce the possibility of pipeline rupture caused...
View Paper titled, Numerical Study on Heat Transfer Enhancement of Modified Wall in U-Tube Steam Generator in LFR
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Topics: Boilers, Heat transfer
Proceedings Papers

Multiscale Thermal-Hydraulic Analysis of the ATHENA Core Simulator

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Pietro Cioli Puviani, Ivan Di Piazza, Ranieri Marinari, Roberto Zanino, Mariano Tarantino
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A064, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93457
https://doi.org/10.1115/ICONE29-93457
... demonstrates the effectiveness of the multiscale approach in reducing the computational cost while maintaining high accuracy in representing the quantities of interest. LFR ALFRED ATHENA CFD porous media Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8...
View Paper titled, Multiscale Thermal-Hydraulic Analysis of the ATHENA Core Simulator
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Topics: Complex systems, Computational fluid dynamics, Design, Fuels, Heating, Manufacturing, Porous materials, Safety, Simulation, Steady state