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Proceedings Papers

Conceptual Design and Feasibility Analysis of a Modular Supercritical CO 2 Fast Reactor Core

Guihua Lai, Tian Wang, Ding She, Hong Wang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A045, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135206
https://doi.org/10.1115/ICONE31-135206
View Paper titled, Conceptual Design and Feasibility Analysis of a Modular Supercritical CO 2 Fast Reactor Core
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Topics: Conceptual design, Fast neutron reactors, Small modular reactors, Supercritical carbon dioxide, Safety, Temperature, Design, Fuel rods, Heat, Particulate matter
Proceedings Papers

Reactivity Feedback Effects of Fuel and Grid Plate Expansion in Small Gas-Cooled Fast Reactors

Yugao Ma, Suyi Zhang, Jian Deng, Jinyu Wang, Yue Liu, Shuhua Ding, Muhao Zhang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A028, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134125
https://doi.org/10.1115/ICONE31-134125
View Paper titled, Reactivity Feedback Effects of Fuel and Grid Plate Expansion in Small Gas-Cooled Fast Reactors
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Topics: Fast neutron reactors, Feedback, Fuels
Proceedings Papers

Study on Thermal-Hydraulic Characteristics of Horizontal Lead-Based Reactor Whole Core

Minyang Gui, Di Wu, Hangyuan Zhang, Senmiao Zhang, Hui Cheng
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A106, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136580
https://doi.org/10.1115/ICONE31-136580
View Paper titled, Study on Thermal-Hydraulic Characteristics of Horizontal Lead-Based Reactor Whole Core
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Topics: Cladding systems (Building), Coolants, Fast neutron reactors, Flow (Dynamics), Gravity (Force), Manufacturing, Nuclear power stations, Power density, Safety, Temperature
Proceedings Papers

Study on the Dynamic Characteristics of the Supercritical CO2 Recompression Brayton Cycle for a Lead-Bismuth Generator Set

Yifan Zhang, Hongzhi Li, Yujia Zhou
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A057, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135095
https://doi.org/10.1115/ICONE31-135095
View Paper titled, Study on the Dynamic Characteristics of the Supercritical CO2 Recompression Brayton Cycle for a Lead-Bismuth Generator Set
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Topics: Brayton cycle, Fast neutron reactors, Generators, Stress, Supercritical carbon dioxide
Proceedings Papers

OpenFOAM-Based Benchmarking Simulations of Xe Gas Behavior in Molten Lead for Advanced Fast Reactors

Emir Hanic, Xiang Wang
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A071, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135256
https://doi.org/10.1115/ICONE31-135256
View Paper titled, OpenFOAM-Based Benchmarking Simulations of Xe Gas Behavior in Molten Lead for Advanced Fast Reactors
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Topics: Fast neutron reactors, Simulation, Alpha decay, Bubbles, Computational fluid dynamics, Computer simulation, Computer software, Cooling, Fluids, Multiphase flow
Proceedings Papers

Study on the Oxidation/Corrosion Behavior of Small Modular Lead-Bismuth-Cooled Fast Reactor Summer

Junjia Zhang, Kefan Zhang, Hongli Chen
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A095, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136020
https://doi.org/10.1115/ICONE31-136020
View Paper titled, Study on the Oxidation/Corrosion Behavior of Small Modular Lead-Bismuth-Cooled Fast Reactor Summer
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Topics: Corrosion, Fast neutron reactors, Oxidation
Proceedings Papers

Numerical Simulation on the Thermal Hydraulic Characteristics in Pool-Type Fast Reactor Based on the New-Designed Passive Dynamic Residual Heat Removal Valve

Yuanshu Qu, Yuhao Zhang, Haiqi Zhao, Daogang Lu
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A073, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135327
https://doi.org/10.1115/ICONE31-135327
View Paper titled, Numerical Simulation on the Thermal Hydraulic Characteristics in Pool-Type Fast Reactor Based on the New-Designed Passive Dynamic Residual Heat Removal Valve
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Topics: Computer simulation, Emergencies, Fast neutron reactors, Heat, Sodium fast reactors, Valves
Proceedings Papers

Prediction of Thermal-Hydraulic Parameters for Autonomous Load Following LFR Core Using Surrogate Model

Kefan Zhang, Wenshun Duan, Junjia Zhang, Hongli Chen
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A052, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134988
https://doi.org/10.1115/ICONE31-134988
View Paper titled, Prediction of Thermal-Hydraulic Parameters for Autonomous Load Following LFR Core Using Surrogate Model
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Topics: Fast neutron reactors, Stress
Proceedings Papers

Numerical Investigation on the Thermal-Hydraulic and FIV Characteristics in LBE-Cooled Helical Cruciform Fuel and Wire-Wrapped Fuel

Qi Zhang, Haoyu Wang, Junxian Cao, Yuanming Li, Chenxi Li, Zhenhai Liu
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A020, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133402
https://doi.org/10.1115/ICONE31-133402
View Paper titled, Numerical Investigation on the Thermal-Hydraulic and FIV Characteristics in LBE-Cooled Helical Cruciform Fuel and Wire-Wrapped Fuel
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Topics: Fast neutron reactors, Flow-induced vibrations, Fuels, Wire
Proceedings Papers

Effect of Corrosion Behavior on the Heat Transfer Performance of Fuel Cladding in Lead-Cooled Fast Reactors

Wenpei Feng, Shangdong Yang, Hongxing Yu, Xingqing Lu, Xue Zhang, Zhixing Gu
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A040, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134758
https://doi.org/10.1115/ICONE31-134758
View Paper titled, Effect of Corrosion Behavior on the Heat Transfer Performance of Fuel Cladding in Lead-Cooled Fast Reactors
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Topics: Cladding systems (Building), Corrosion, Fast neutron reactors, Fuels, Heat transfer
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

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
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
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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

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
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

Effect of Different P/D Ratios on the Thermal-Hydraulic Performance of Fuel Assemblies in a Lead-Cooled Fast Reactor

Yangguang Zhang, Daogang Lu, Qiong Cao, Xiaotian Wang
Proc. ASME. ICONE31, Volume 7: Computational Fluid Dynamics (CFD) and Applications, V007T08A020, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135052
https://doi.org/10.1115/ICONE31-135052
View Paper titled, Effect of Different P/D Ratios on the Thermal-Hydraulic Performance of Fuel Assemblies in a Lead-Cooled Fast Reactor
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Topics: Fast neutron reactors, Fuels, Manufacturing
Proceedings Papers

Multi-Physics Coupling Simulation of a Small Floating Lead-Cooled Fast Reactor Based on OpenMC and GeN-Foam

Haochen Huang, Fei Xie, Yu Liu, Daogang Lu
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A011, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135154
https://doi.org/10.1115/ICONE31-135154
View Paper titled, Multi-Physics Coupling Simulation of a Small Floating Lead-Cooled Fast Reactor Based on OpenMC and GeN-Foam
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Topics: Fast neutron reactors, Physics, Simulation
Proceedings Papers

Pure Lead Thermodynamic Properties in SIMMER-III Code: A Comparative Review and New Evaluation Proposal

Alessandro Bellomo, Mattia Massone, Simone Gianfelici, Koji Morita, Mariano Tarantino, Alessio Pesetti, Vittorio Cossu, Andrei Rineiski
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T13A016, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136243
https://doi.org/10.1115/ICONE31-136243
View Paper titled, Pure Lead Thermodynamic Properties in SIMMER-III Code: A Comparative Review and New Evaluation Proposal
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Topics: Equations of state, Fast neutron reactors, Thermodynamic properties, Heat capacity, Accidents, Design, Liquid metals, Pressure, Sodium fast reactors, Boilers
Proceedings Papers

Numerical Investigation of Postulated Steam Generator Tube Rupture Accident in a Lead-Cooled Fast Reactor

Yutong Chen, Dalin Zhang, Zhenyu Feng, Yue Lin, Wenxi Tian, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A024, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134478
https://doi.org/10.1115/ICONE31-134478
View Paper titled, Numerical Investigation of Postulated Steam Generator Tube Rupture Accident in a Lead-Cooled Fast Reactor
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Topics: Accidents, Boilers, Fast neutron reactors, Rupture
Proceedings Papers

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

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
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

Research on Multi-Scale Coupling Program Based on Lead Bismuth Fast Reactor

Yixin Zhang, Chenglong Wang, Jiaxin Zhang, Wenxi Tian, S. Z. Qiu, G. H. Su
Proc. ASME. ICONE31, Volume 11: Student Paper Competition, V011T15A057, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135354
https://doi.org/10.1115/ICONE31-135354
View Paper titled, Research on Multi-Scale Coupling Program Based on Lead Bismuth Fast Reactor
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Topics: Fast neutron reactors, Transients (Dynamics)
Proceedings Papers

Stress Intensity Factor Solutions for Circumferential Through-Wall Cracks Applicable to Pool Type Sodium Cooled Fast Reactors

Hiroki Yada, Shigeru Takaya, Hideo Machida
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A010, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134552
https://doi.org/10.1115/ICONE31-134552
View Paper titled, Stress Intensity Factor Solutions for Circumferential Through-Wall Cracks Applicable to Pool Type Sodium Cooled Fast Reactors
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Topics: Cylinders, Fast neutron reactors, Finite element analysis, Fracture (Materials), Sodium, Stress
Proceedings Papers

Implementation and Comparison of Super Homogenization Method Based on Monte Carlo and Deterministic Codes

Yuan Yuan, Guoming Liu, Xiaodong Huo
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A006, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92520
https://doi.org/10.1115/ICONE29-92520
View Paper titled, Implementation and Comparison of Super Homogenization Method Based on Monte Carlo and Deterministic Codes
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Topics: Chemical kinetics, Cross section (Physics), Fast neutron reactors, Geometry, Manufacturing, Modeling, Physics, Relaxation (Physics), Very high temperature reactors