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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89079
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93095
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
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Topics: Absorption, Cladding systems (Building), Deformation, Design, Irradiation (Radiation exposure), Neutrons, Pressurized water reactors, Rods, Safety, Shock absorbers
Proceedings Papers

Development and Verification of Multigroup Cross Section Generation Module GroupXS in AXSP

Kui Hu, Xubo Ma, Xuan Ma, Chen Zhang, Guanqun Jia, Yixue Chen
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A031, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91399
https://doi.org/10.1115/ICONE29-91399
View Paper titled, Development and Verification of Multigroup Cross Section Generation Module GroupXS in AXSP
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Topics: Approximation, Cross section (Physics), Errors, Intellectual property, Neutrons, Nuclear reactors, Nuclides, Physics
Proceedings Papers

Development and Verification of Neutron and Photon Ultrafine Group Library for Fast Reactor Physical Calculation

Teng Zhang, Xubo Ma, Guanqun Jia, Xuan Ma, Bin Zhang, Kui Hu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A046, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92091
https://doi.org/10.1115/ICONE29-92091
View Paper titled, Development and Verification of Neutron and Photon Ultrafine Group Library for Fast Reactor Physical Calculation
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Topics: Fast neutron reactors, Neutrons, Photons
Proceedings Papers

Molten Salt Reactor Experiment Simulation Using ThorMOC

Ao Zhang, Ming Dai, Maosong Cheng, Jingen Chen
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A014, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90510
https://doi.org/10.1115/ICONE29-90510
View Paper titled, Molten Salt Reactor Experiment Simulation Using ThorMOC
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Topics: Molten salt reactors, Simulation, Modeling, Eigenvalues, Graphics processing units, Neutrons, Nuclear reactors
Proceedings Papers

Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies

Jian Li, Ruihan Li, Ding She, Jin'gang Liang, Lei Shi
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89241
https://doi.org/10.1115/ICONE29-89241
View Paper titled, Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies
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Topics: Heat, Pressurized water reactors, Spent nuclear fuels, Fuels, Neutrons, Boiling water reactors, Collapse, Cooling, Cross section (Physics), Density
Proceedings Papers

Research Progress of Neutron Shielding Materials

Bing Chang, Saisai Li, Minghui Li, Ruoyu Chen
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A050, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92210
https://doi.org/10.1115/ICONE29-92210
View Paper titled, Research Progress of Neutron Shielding Materials
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Topics: Metals, Neutrons, Polymers
Proceedings Papers

A Discrete-Ordinates Variational Nodal Method for Solving Multi-Dimensional Neutron Transport Equation With Unstructured Mesh

Qizheng Sun, Tengfei Zhang, Xiaojing Liu, Xiang Chai, Jinbiao Xiong
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A034, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91525
https://doi.org/10.1115/ICONE29-91525
View Paper titled, A Discrete-Ordinates Variational Nodal Method for Solving Multi-Dimensional Neutron Transport Equation With Unstructured Mesh
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Topics: Neutrons
Proceedings Papers

Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors

Doctor Enivweru, Qingyu Wang, Abiodun Ayodeji, John Njoroge
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A021, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90736
https://doi.org/10.1115/ICONE29-90736
View Paper titled, Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors
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Topics: Corrosion, Fuels, Hydrogen embrittlement, Pressurized water reactors, Cladding systems (Building), Hydrogen, Temperature, Accidents, Boundary-value problems, Coolants
Proceedings Papers

The Optimal Theta of Optimally Diffusive Coarse Mesh Finite Difference Method to Accelerate DGFEM Based SN

Boran Kong, Han Zhang, Kaijie Zhu, Chen Hao, Jiong Guo, Fu Li
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A006, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89221
https://doi.org/10.1115/ICONE29-89221
View Paper titled, The Optimal Theta of Optimally Diffusive Coarse Mesh Finite Difference Method to Accelerate DGFEM Based SN
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Topics: Diffusion (Physics), Eigenvalues, Electromagnetic scattering, Finite difference methods, Fittings, Fourier analysis, Neutrons, Polynomials, Radiation scattering, Scattering (Physics)
Proceedings Papers

Numerical Simulation of Reactor Neutron Noise Based on Discrete Ordinate Finite Element Method

Baoxin Yuan, Xin Luo, Herong Zeng, Huan Huang, Jie Zheng, Wankui Yang, Songbao Zhang, Bin Zhong, Junxia Wei, Yangjun Ying
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A036, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91726
https://doi.org/10.1115/ICONE29-91726
View Paper titled, Numerical Simulation of Reactor Neutron Noise Based on Discrete Ordinate Finite Element Method
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Topics: Computer simulation, Finite element analysis, Finite element methods, Neutrons, Noise (Sound)
Proceedings Papers

Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non-Dominated Sorting

Rui Li, Shichang Liu
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A027, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90902
https://doi.org/10.1115/ICONE29-90902
View Paper titled, Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non-Dominated Sorting
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Topics: Nuclear reactors, Nuclides, Radiation (Physics), Neutrons, Cross section (Physics), Monte Carlo methods, Photons, Absorption, Databases, Elastic scattering
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90146
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)
Proceedings Papers

Dynamic Precision Evaluation of Compensated Ion-Chambers for Reactor Power Monitoring

Qichang Huang, Mingxing Liu
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A024, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92460
https://doi.org/10.1115/ICONE29-92460
View Paper titled, Dynamic Precision Evaluation of Compensated Ion-Chambers for Reactor Power Monitoring
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Topics: Ionization chambers, Neutrons
Proceedings Papers

TCR Central Shutdown Rod Fine Motion Control

Venugopal K. Varma, Eliott Fountain, Earle Burkhardt, Sacit Cetiner, Dustin Ottinger
Proc. ASME. ICONE29, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90217
https://doi.org/10.1115/ICONE29-90217
View Paper titled, TCR Central Shutdown Rod Fine Motion Control
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Topics: Electromagnets, Motion control, Design, Pressure vessels, Actuators, Artificial intelligence, Engineering prototypes, Engines, Gravity (Force), Helium
Proceedings Papers

Neutronics Design and Modelling of a Nuscale-Based Small Modular PWR

Yanfei Qiu
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A033, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93201
https://doi.org/10.1115/ICONE29-93201
View Paper titled, Neutronics Design and Modelling of a Nuscale-Based Small Modular PWR
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Topics: Design, Modeling, Pressurized water reactors, Cycles, Fuels, Safety, Feedback, Modular construction, Neutrons, Nuclear reactors
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93256
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

3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core

Qing Yang, Jianhua Xia, Xiaojing Liu, Qingquan Pan, Hui He, Tengfei Zhang
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A038, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-94534
https://doi.org/10.1115/ICONE29-94534
View Paper titled, 3d Multi-Physics Numerical Coupling of Monte Carlo Neutronics and Thermal-Hydraulic for Solid Core
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Topics: Physics, Neutrons, Simulation, Computational fluid dynamics, Computer simulation, Conceptual design, Coolants, Design, Nuclear design, Optimization
Proceedings Papers

Study on the Plutonium Holdup Measurement in Glove-Box

Yimei Cheng, Xiaoming Xu, Honghe Yin, Xinjun Li, Sijia Wang
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90455
https://doi.org/10.1115/ICONE29-90455
View Paper titled, Study on the Plutonium Holdup Measurement in Glove-Box
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Topics: Design, Electronics, Measurement systems, Neutrons, Optimization, Sensors, Simulation, Stability
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92104
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)