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Proceedings Papers

Verification and Validation of JMCT Monte Carlo Code in CPR1000

Yaoxin Ye, Jun Zhao, Pengfei Bao
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A009, August 8–12, 2022
Paper No: ICONE29-93545
DOI: https://doi.org/10.1115/ICONE29-93545
View Paper titled, Verification and Validation of JMCT Monte Carlo Code in CPR1000
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Topics: China, Computer technology, Design, Fluence (Radiation measurement), Irradiation (Radiation exposure), Monte Carlo methods, Neutrons, Nuclear engineering, Nuclear power stations, Particulate matter
Proceedings Papers

Analysis of Radiation-Induced Demagnetization Influence on the Performance of Permanent Magnet Damper

Hongyu Wu, He Yan, Xingzhong Diao
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A027, August 8–12, 2022
Paper No: ICONE29-90515
DOI: https://doi.org/10.1115/ICONE29-90515
View Paper titled, Analysis of Radiation-Induced Demagnetization Influence on the Performance of Permanent Magnet Damper
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Topics: Dampers, Irradiation (Radiation exposure), Neutrons, Permanent magnets, Radiation (Physics)
Proceedings Papers

Modelling the Brittle-Ductile Transition Temperature of Irradiated A508-3 Steel With CPFEM

Pandong Lin, Junfeng Nie, Meidan Liu
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A035, August 8–12, 2022
Paper No: ICONE29-90986
DOI: https://doi.org/10.1115/ICONE29-90986
View Paper titled, Modelling the Brittle-Ductile Transition Temperature of Irradiated A508-3 Steel With CPFEM
Click here to open pdf in another window PDF for Modelling the Brittle-Ductile Transition Temperature of Irradiated A508-3 Steel With CPFEM
Topics: Brittleness, Embrittlement, Irradiation (Radiation exposure), Modeling, Phase transition temperature, Steel
Proceedings Papers

Simulation of Neutron and Proton Displacement Damage in Ultra-Wide Bandgap Semiconductor Ga 2 O 3

Zhuang Shao, Ziqi Cai, Qingmin Zhang
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A027, August 8–12, 2022
Paper No: ICONE29-92600
DOI: https://doi.org/10.1115/ICONE29-92600
View Paper titled, Simulation of Neutron and Proton Displacement Damage in Ultra-Wide Bandgap Semiconductor Ga 2 O 3
Click here to open pdf in another window PDF for Simulation of Neutron and Proton Displacement Damage in Ultra-Wide Bandgap Semiconductor Ga 2 O 3
Topics: Damage, Displacement, Energy gap, Irradiation (Radiation exposure), Neutrons, Protons, Semiconductors (Materials), Simulation
Proceedings Papers

Numerical Simulation of Flow Resistance Characteristics In the Test Section of a Rodlet Fuel Irradiation Device

Jin Shuai, Yang Wenhua, Lei Jin, Zhang Liang, Sun Sheng, Zhao Wenbin
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A035, August 8–12, 2022
Paper No: ICONE29-92225
DOI: https://doi.org/10.1115/ICONE29-92225
View Paper titled, Numerical Simulation of Flow Resistance Characteristics In the Test Section of a Rodlet Fuel Irradiation Device
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Topics: Computational fluid dynamics, Computer simulation, Flow (Dynamics), Fuels, Irradiation (Radiation exposure)
Proceedings Papers

Investigation on Irradiation Resistance of Anti-Galling Lubricant for High Temperature Fasteners of Nuclear Power Plant

Xiao Qiang Liu, Ming Jiao, Xiu Qiang Shi, Yichen Bao
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A025, August 8–12, 2022
Paper No: ICONE29-92166
DOI: https://doi.org/10.1115/ICONE29-92166
View Paper titled, Investigation on Irradiation Resistance of Anti-Galling Lubricant for High Temperature Fasteners of Nuclear Power Plant
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Topics: Fasteners, Galling, High temperature, Irradiation (Radiation exposure), Lubricants, Nuclear power stations, Oxidation
Proceedings Papers

Research and Development of SA508Gr.4N Steel Ultra-Thick Forgings With High Strength and Toughness for Nuclear Engineering

Dongxu Du, Deli Zhao, Liguo Ren, Wenhui Zhang, Jiaju Li, Xikou He
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A031, August 8–12, 2022
Paper No: ICONE29-92329
DOI: https://doi.org/10.1115/ICONE29-92329
View Paper titled, Research and Development of SA508Gr.4N Steel Ultra-Thick Forgings With High Strength and Toughness for Nuclear Engineering
Click here to open pdf in another window PDF for Research and Development of SA508Gr.4N Steel Ultra-Thick Forgings With High Strength and Toughness for Nuclear Engineering
Topics: Embrittlement, Forgings (Products), Fracture toughness, Industrial research, Irradiation (Radiation exposure), Nuclear engineering, Steel
Proceedings Papers

Light Water-Cooled High-Performance Research Reactor Physics Design and Analysis

Zihao Guo, Guang Wang, Genghua Su, Xiuan Shi
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A036, August 8–12, 2022
Paper No: ICONE29-93256
DOI: https://doi.org/10.1115/ICONE29-93256
View Paper titled, Light Water-Cooled High-Performance Research Reactor Physics Design and Analysis
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Topics: Design, Irradiation (Radiation exposure), Neutron flux, Physics, Water, Biomedicine, Isotopes, Cycles, Decontamination, Fuels
Proceedings Papers

Preliminary Study on the Migration of Polonium-210 in Lead-Based Fast Reactor

Yali Qiu, Qin Zeng, Hongli Chen
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A031, August 8–12, 2022
Paper No: ICONE29-92104
DOI: https://doi.org/10.1115/ICONE29-92104
View Paper titled, Preliminary Study on the Migration of Polonium-210 in Lead-Based Fast Reactor
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Topics: Fast neutron reactors, Radioisotopes, Coolants, Volatility, Accidents, Circuits, Computational fluid dynamics, Containment, Hazards, Irradiation (Radiation exposure)
Proceedings Papers

Thermal Analysis and Optimization of the Heat Exchange System in the Test Loop for the Fuel Assembly Steady-State Irradiation Based on a Re-Evaluation Method

Si Junping, Liu Xiaosong, Zhao Wenbin, Xu Yuheng, Lei Jin, Zhang Wenlong, Huang Gang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A031, August 8–12, 2022
Paper No: ICONE29-90468
DOI: https://doi.org/10.1115/ICONE29-90468
View Paper titled, Thermal Analysis and Optimization of the Heat Exchange System in the Test Loop for the Fuel Assembly Steady-State Irradiation Based on a Re-Evaluation Method
Click here to open pdf in another window PDF for Thermal Analysis and Optimization of the Heat Exchange System in the Test Loop for the Fuel Assembly Steady-State Irradiation Based on a Re-Evaluation Method
Topics: Fuels, Heat, High temperature, Irradiation (Radiation exposure), Manufacturing, Optimization, Steady state, Thermal analysis, Water
Proceedings Papers

Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod

Kaiyuan Wang, Xiaohan Liu, Xin Jin
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A021, August 8–12, 2022
Paper No: ICONE29-89917
DOI: https://doi.org/10.1115/ICONE29-89917
View Paper titled, Analysis and Evaluation of Performance for Enriched B 4 C Absorber Used as Control Rod
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Topics: Absorption, Boron, Cladding systems (Building), Corrosion resistance, Design, Fuels, Irradiation (Radiation exposure), Manufacturing, Neutrons, Nuclear fission
Proceedings Papers

Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature

Xiangyu Wei, Wenhua Zhang, Yingchun Zhao
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A079, August 8–12, 2022
Paper No: ICONE29-93417
DOI: https://doi.org/10.1115/ICONE29-93417
View Paper titled, Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature
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Topics: Atmospheric pressure, Fuels, Ropes, Temperature, Cladding systems (Building), Stress, Fuel rods, Irradiation (Radiation exposure), Pressure, Sensitivity analysis
Proceedings Papers

Study on Ultrasonic Inspection Technology of Fastening Bolts of Reactor Internals

Jianbang Tang, Yukun Wu, Weiqiang Wang, Guanbing Ma, Chenming Zeng, Junlong Xu
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A048, August 8–12, 2022
Paper No: ICONE29-92644
DOI: https://doi.org/10.1115/ICONE29-92644
View Paper titled, Study on Ultrasonic Inspection Technology of Fastening Bolts of Reactor Internals
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Topics: Inspection, Nuclear power stations, Nondestructive evaluation, Design, High pressure (Physics), High temperature, In-service inspection, Irradiation (Radiation exposure), Nuclear fuels, Probes
Proceedings Papers

Microstructural Evolution of SiC-Coated C/C Composites Under Argon Ion Irradiation

Xiangmin Xie, Long Yan, Guodong Cheng, Xian Tang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A011, August 8–12, 2022
Paper No: ICONE29-90325
DOI: https://doi.org/10.1115/ICONE29-90325
View Paper titled, Microstructural Evolution of SiC-Coated C/C Composites Under Argon Ion Irradiation
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Topics: Coatings, Composite materials, Irradiation (Radiation exposure)
Proceedings Papers

Creep Properties of FeCrAl Alloy at High Temperature Under Neutron Irradiation

Huan Yao, Tianzhou Ye, Junmei Wu, Yingwei Wu, Chunyu Yin, Ping Chen
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A005, August 8–12, 2022
Paper No: ICONE29-89079
DOI: https://doi.org/10.1115/ICONE29-89079
View Paper titled, Creep Properties of FeCrAl Alloy at High Temperature Under Neutron Irradiation
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Topics: Alloys, Creep, High temperature, Irradiation (Radiation exposure), Neutrons
Proceedings Papers

Analysis of the Influence of RCCA Swelling on Rod Falling and Study on Mitigation Measures

Zhipeng Lv, Guoliang Zhang, Changzheng Li, Weichao Liu, Shaofang Lin, Lihong Nie, Zhijun Li, Anlong Zhang
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A067, August 8–12, 2022
Paper No: ICONE29-93095
DOI: https://doi.org/10.1115/ICONE29-93095
View Paper titled, Analysis of the Influence of RCCA Swelling on Rod Falling and Study on Mitigation Measures
Click here to open pdf in another window PDF for Analysis of the Influence of RCCA Swelling on Rod Falling and Study on Mitigation Measures
Topics: Absorption, Cladding systems (Building), Deformation, Design, Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Rods, Safety, Shock absorbers
Proceedings Papers

Design and Investigation of Liquid Lead-Bismuth Test Irradiation Loop in Research Reactor

Yuheng Xu, Juping Si, Liang Zhang, Sheng Sun, Hongwei Wu, Mengkang Lu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A032, August 8–12, 2022
Paper No: ICONE29-91405
DOI: https://doi.org/10.1115/ICONE29-91405
View Paper titled, Design and Investigation of Liquid Lead-Bismuth Test Irradiation Loop in Research Reactor
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Topics: Design, Irradiation (Radiation exposure)
Proceedings Papers

Study and Development of Irradiation Test Device for Fuel Rods In Research Reactor

Wenbin Zhao, Junping Si, Liang Zhang, Sheng Sun, Wenhua Yang, Shuai Jin, Jin Lei, Hao Liu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A028, August 8–12, 2022
Paper No: ICONE29-90997
DOI: https://doi.org/10.1115/ICONE29-90997
View Paper titled, Study and Development of Irradiation Test Device for Fuel Rods In Research Reactor
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Topics: Fuel rods, Irradiation (Radiation exposure)
Proceedings Papers

A Digital Proof of Concept (POC) for Simulating the Coupled Phenomena Between Neutronics, Structural and Fluid Dynamics in a Reactor Core

Jie Liu, Chunyu Zhang, Zhihao Zheng, Jiesheng Min
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A073, August 8–12, 2022
Paper No: ICONE29-93008
DOI: https://doi.org/10.1115/ICONE29-93008
View Paper titled, A Digital Proof of Concept (POC) for Simulating the Coupled Phenomena Between Neutronics, Structural and Fluid Dynamics in a Reactor Core
Click here to open pdf in another window PDF for A Digital Proof of Concept (POC) for Simulating the Coupled Phenomena Between Neutronics, Structural and Fluid Dynamics in a Reactor Core
Topics: Fluid dynamics, Physics, Simulation, Computational fluid dynamics, Structural analysis, American Petroleum Institute, Computation, Computer simulation, Computer software, Computer-aided engineering
Proceedings Papers

Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor

Hu Ziao, Chen Xiao-xian, Chen Xiao-liang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A010, August 8–12, 2022
Paper No: ICONE29-90146
DOI: https://doi.org/10.1115/ICONE29-90146
View Paper titled, Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor
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Topics: China, Damage, Design, Fast neutron reactors, Irradiation (Radiation exposure), Neutron flux, Radiation damage, Sensors, Neutrons, Cladding systems (Building)