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Proceedings Papers

Structure Control of a HLW Immobilized Zirconolite Glass-Ceramic Matrix

Haiqing Li, Yutong Pan, Chao Gao, Shuming Wang
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A036, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93212
https://doi.org/10.1115/ICONE29-93212
View Paper titled, Structure Control of a HLW Immobilized Zirconolite Glass-Ceramic Matrix
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Topics: Ceramics, Glass, Glass ceramics, Crystallization, Temperature, Crystals, Durability, Heat treating (Metalworking), Nucleation (Physics), Nuclides
Proceedings Papers

Study on the Substitute Nuclides of Actinides in High-Level Radioactive Waste Liquid

Yingzhe Du, Lili Li, Kunfeng Li, Peng Lin, Yugang Zhang, Juan Diwu
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A040, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93771
https://doi.org/10.1115/ICONE29-93771
View Paper titled, Study on the Substitute Nuclides of Actinides in High-Level Radioactive Waste Liquid
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Topics: Nuclides, Radioactive wastes, Glass, Solidification, Chemical properties, Electron configuration, Molecular orbitals, Nuclear reactions, Oxidation
Proceedings Papers

Simulation Research on Real-Time Offsite Dose Radiation of Nuclear Power Plant

Pingwen Ou, Zhenghui Wang, Dongyu He, Pingting Jiang
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91568
https://doi.org/10.1115/ICONE29-91568
View Paper titled, Simulation Research on Real-Time Offsite Dose Radiation of Nuclear Power Plant
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Topics: Emergencies, Nuclear power stations, Radiation (Physics), Simulation, Safety, Accidents, Plumes (Fluid dynamics), Diffusion (Physics), Economics , Emergency response
Proceedings Papers

Validation of NUIT for Nuclides Composition Calculation With PWR Spent Fuel Isotropic Measurement

Kai Tan, Ruihan Li, Jian Li, Jingang Liang, Ding She
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A053, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91659
https://doi.org/10.1115/ICONE29-91659
View Paper titled, Validation of NUIT for Nuclides Composition Calculation With PWR Spent Fuel Isotropic Measurement
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Topics: Nuclides, Pressurized water reactors, Spent nuclear fuels, Density, Errors, Accuracy and precision, Fuels, Heat, Isotopes, Nuclear fission
Proceedings Papers

Summary of Methods for Studying the Chemical States of Nuclides In Nuclear Energy Systems

Jingni Guo, Yu Wang, Ziling Zhou, Feng Xie, Jiejuan Tong, Kerong Wang, Peng Li, Jing Jiang
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A032, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90873
https://doi.org/10.1115/ICONE29-90873
View Paper titled, Summary of Methods for Studying the Chemical States of Nuclides In Nuclear Energy Systems
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Topics: Chemical reactions, Nuclear power, Nuclides, Computer software, Bonding, Chemical properties, Chemistry, Desorption, Diffusion processes, Equilibrium (Physics)
Proceedings Papers

Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium

Ziling Zhou, Yu Wang, Jingni Guo, Feng Xie, Wenqian Li, Yanwei Wen, Bin Shan
Proc. ASME. ICONE29, Volume 15: Student Paper Competition, V015T16A039, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91275
https://doi.org/10.1115/ICONE29-91275
View Paper titled, Summary of Effects of Oxide Layer on Permeability Coefficient of Tritium
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Topics: Hydraulic conductivity, Very high temperature reactors, Fusion reactors, Hydrogen, Isotopes, Nuclear reactors, Coolants, Design, Diffusion (Physics), Engineering systems and industry applications
Proceedings Papers

Investigation of the Fuel Element Damage Monitoring Technology in HTGRs and PWRs

Rui Nie, Yu Wang, Feng Xie, Shan Qing, Jianzhu Cao
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A002, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-88883
https://doi.org/10.1115/ICONE29-88883
View Paper titled, Investigation of the Fuel Element Damage Monitoring Technology in HTGRs and PWRs
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Topics: Damage, Fuels, Nuclides, Pressurized water reactors, Very high temperature reactors
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

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

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

Analysis of Interfacing Systems LOCA for RIS-RHR System Under Full Pressure Conditions

Guogang Bao, Changdong Lu, Weiwei Wang, Ren Liang, Zhikang Lin, Yong Ouyang
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A013, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89383
https://doi.org/10.1115/ICONE29-89383
View Paper titled, Analysis of Interfacing Systems LOCA for RIS-RHR System Under Full Pressure Conditions
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Topics: Accidents, Cladding systems (Building), Coolants, Damage, Fuel rods, Heat, Pressure, Resonance ionization spectroscopy, Safety, Leakage
Proceedings Papers

Further Study on Real-Time Positioning of Fuel Failures Method in HFETR

Shouhua Sun, Jian Li
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64210
https://doi.org/10.1115/ICONE28-64210
View Paper titled, Further Study on Real-Time Positioning of Fuel Failures Method in HFETR
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Topics: Failure, Fuels, Radioisotopes, Chain, Cladding systems (Building), Coolants, Corrosion, Damage, Fracture (Materials), Manufacturing
Proceedings Papers

Study on Main Radionuclides of Liquid Waste in Containment Under Severe Accident

Shaowei Wang, Haiying Chen, Wei Li
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A021, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64403
https://doi.org/10.1115/ICONE28-64403
View Paper titled, Study on Main Radionuclides of Liquid Waste in Containment Under Severe Accident
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Topics: Accidents, Containment, Nuclides, Radioisotopes
Proceedings Papers

Estimation of the Amount of I-129 in the Environment Generated Due to the Decay of Te-129m Discharged by the Fukushima NPS Accident

Haruo Sato
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T11A013, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65725
https://doi.org/10.1115/ICONE28-65725
View Paper titled, Estimation of the Amount of I-129 in the Environment Generated Due to the Decay of Te-129m Discharged by the Fukushima NPS Accident
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Topics: Accidents, Fukushima nuclear disaster, Japan, 2011, Soil, Half-life, Radioisotopes, Earthquakes, Equilibrium (Physics), Nuclear power stations, Nuclides, Radiation (Physics)
Proceedings Papers

Research of a Fast Sample Preparation Method for Water Radioactivity Measurement

Shuijun He, Xiangwei Wang, Manchun Liang, Guofeng Su, Anying Chen, Chao Zhang, Ke Li
Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T11A003, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-60437
https://doi.org/10.1115/ICONE28-60437
View Paper titled, Research of a Fast Sample Preparation Method for Water Radioactivity Measurement
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Topics: Radiation measurement, Water, Boiling, Emergencies, Low temperature, Nuclides, Radioactivity, Radioisotopes, Vacuum
Proceedings Papers

Research on Tritium Behavior Issues in High-Temperature Gas-Cooled Reactors

Ziling Zhou, Chuan Li, Nan Gui, Feng Xie, Yanwei Wen, Bin Shan, Jia Fu, Qunchao Fan
Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A016, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63539
https://doi.org/10.1115/ICONE28-63539
View Paper titled, Research on Tritium Behavior Issues in High-Temperature Gas-Cooled Reactors
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Topics: Diffusion (Physics), Isotopes, Very high temperature reactors, Coolants, Graphite, Absorption, Desorption, Safety, Engineering prototypes, Fuels
Proceedings Papers

Metamorphic Testing on Nuclide Inventory Tool

Meng Li, Shiyu Yan, Xiaohua Yang, Jie Liu
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A001, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16403
https://doi.org/10.1115/ICONE2020-16403
View Paper titled, Metamorphic Testing on Nuclide Inventory Tool
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Topics: Nuclides, Testing, Algorithms, Approximation, Computer software, Nuclear magnetic resonance, Physics, Software development
Proceedings Papers

Evaluation of Heat Removal During the Failure of the Core Cooling for New Critical Assembly

Yuta Eguchi, Takanori Sugawara, Kenji Nishihara, Yujiro Tazawa, Kazufumi Tsujimoto
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A020, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82012
https://doi.org/10.1115/ICONE26-82012
View Paper titled, Evaluation of Heat Removal During the Failure of the Core Cooling for New Critical Assembly
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Topics: Cooling, Failure, Heat, Manufacturing, Design, Temperature, Cooling systems, Heat transfer coefficients, Fuels, Heat transfer
Proceedings Papers

Analysis and Improvement of Global-Local Self-Shielding Calculation Scheme for AIC Control Rods

Jikui Li, Tiejun Zu, Liangzhi Cao, HongChun Wu, Qingming He
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A045, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82196
https://doi.org/10.1115/ICONE26-82196
View Paper titled, Analysis and Improvement of Global-Local Self-Shielding Calculation Scheme for AIC Control Rods
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Topics: Rods, Resonance, Errors, Absorption, Fuels, Cross section (Physics), Neutrons, Nuclear reactors, Nuclides, Physics
Proceedings Papers

Research on Coupling Scheme of Monte Carlo Burnup Calculation in RMC

Wanlin Li, Kan Wang, Ganglin Yu, Yaodong Li
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A005, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81140
https://doi.org/10.1115/ICONE26-81140
View Paper titled, Research on Coupling Scheme of Monte Carlo Burnup Calculation in RMC
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Topics: Approximation, Computational methods, Cross section (Physics), Density, Design, Errors, Geometry, Manufacturing, Modeling, Neutron flux