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Proceedings Papers

Research on Scenarios and Development Paths of China’s Commercial Closed Nuclear Fuel Cycle

Min Xiao, Xiaojun Xiao
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A007, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89223
https://doi.org/10.1115/ICONE29-89223
View Paper titled, Research on Scenarios and Development Paths of China’s Commercial Closed Nuclear Fuel Cycle
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Topics: Nuclear fuel cycle, Pressurized water reactors
Proceedings Papers

Research on the Influence of Degassing on the Release of Fission Gases in PWRs

Yaoxin Ye, Pengtao Fu, Zhijun Li
Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A008, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89461
https://doi.org/10.1115/ICONE29-89461
View Paper titled, Research on the Influence of Degassing on the Release of Fission Gases in PWRs
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Topics: Failure, Fuels, Gases, Nuclear fission, Pressurized water reactors, Coolants, Nuclear power stations, Cladding systems (Building), Nuclear fuel cycle, Rods
Proceedings Papers

Modelica Based Economic Analysis of Nuclear Fuel Cycle

Jie Liu, Xiang Wang
Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A035, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91600
https://doi.org/10.1115/ICONE29-91600
View Paper titled, Modelica Based Economic Analysis of Nuclear Fuel Cycle
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Topics: Economic analysis, Economics , Nuclear fuel cycle
Proceedings Papers

Study on Time-Dependent Co-58 and Co-60 Activities in the Primary Coolant of CPR1000 PWRs

Xiaoqian Zhang, Pengtao Fu
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A034, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92822
https://doi.org/10.1115/ICONE29-92822
View Paper titled, Study on Time-Dependent Co-58 and Co-60 Activities in the Primary Coolant of CPR1000 PWRs
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Topics: Boiling, Coolants, Corrosion, Pressurized water reactors, Radioisotopes, Cycles, Circuits, Maintenance, Shapes, Cobalt
Proceedings Papers

High Efficient Mineralization of Cesium in Waste Liquid by Hydrothermal Method

Kai Gao, Wendong Feng, Xiaojun Yan, Xiaobin Guo, Xiaoyan Cui, Xiliang Guo
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90716
https://doi.org/10.1115/ICONE29-90716
View Paper titled, High Efficient Mineralization of Cesium in Waste Liquid by Hydrothermal Method
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Topics: Aluminum, Cements (Adhesives), Exhaust systems, Glass, High temperature, Ion exchange, Nuclear fuel cycle, Phase transition temperature, Raw materials, Sewage
Proceedings Papers

Modeling and Analysis of Tritium Fuel Cycle for Magnetic Confinement Fusion Reactor

Jinggang Xu, Qin Zeng, Sheng Wang, Huaihuai Wang, Junjie Zhou, Yangbin Xiong, Jingchen Yang
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A007, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90643
https://doi.org/10.1115/ICONE29-90643
View Paper titled, Modeling and Analysis of Tritium Fuel Cycle for Magnetic Confinement Fusion Reactor
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Topics: Magnetic fusion, Modeling, Nuclear fuel cycle
Proceedings Papers

Study on the Applicability of Typical Valve Failure Data to Non-Reactor Nuclear Fuel Cycle Front-End Facilities

Dan Lyu, Xiao-wei Yang, Yan Lu, Shi-jun Wang, Chun-yan Xu
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A005, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63354
https://doi.org/10.1115/ICONE28-63354
View Paper titled, Study on the Applicability of Typical Valve Failure Data to Non-Reactor Nuclear Fuel Cycle Front-End Facilities
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Topics: Failure, Failure data, Nuclear fuel cycle, Valves
Proceedings Papers

Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor

Xuesong Yan, Yaling Zhang, Yucui Gao, Lei Yang
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T03A008, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65406
https://doi.org/10.1115/ICONE28-65406
View Paper titled, Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor
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Topics: Ceramics, Fast neutron reactors, High temperature, Neutrons, Nuclear fuel cycle, Physics, Spent nuclear fuels
Proceedings Papers

Tritium Transport Modeling and Analysis for HCCB Blanket of CFETR

Baorui Zhang, Zhaoyang Xia, Zhiwei Zhou
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, V003T08A017, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-65076
https://doi.org/10.1115/ICONE28-65076
View Paper titled, Tritium Transport Modeling and Analysis for HCCB Blanket of CFETR
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Topics: Ceramics, China, Computational fluid dynamics, Coolants, Design, Discrete element methods, Flow (Dynamics), Fusion reactors, Helium, Modeling
Proceedings Papers

A Beyond Design Basis Earthquake Study of Operating Nuclear Fuel Cycle Facilities

Li Liang, Pan Rong, Zhu Xiuyun, Ren Guopeng
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, V003T12A026, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64514
https://doi.org/10.1115/ICONE28-64514
View Paper titled, A Beyond Design Basis Earthquake Study of Operating Nuclear Fuel Cycle Facilities
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Topics: Design, Earthquakes, Nuclear fuel cycle, Safety
Proceedings Papers

The Safety of Nuclear Fuel Cycle Facilities in China After the Fukushima Accident

Ji Que, Xiao-wei Yang, Yun-tao Liu, Shan-gui Zhao, Hong Shen, Tian-Shu Liu
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, V003T12A017, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64258
https://doi.org/10.1115/ICONE28-64258
View Paper titled, The Safety of Nuclear Fuel Cycle Facilities in China After the Fukushima Accident
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Topics: China, Fukushima nuclear disaster, Japan, 2011, Nuclear fuel cycle, Safety
Proceedings Papers

A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations

Jaakko Leppänen, Ville Valtavirta, Riku Tuominen, Antti Rintala, Unna Lauranto
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T04A010, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64347
https://doi.org/10.1115/ICONE28-64347
View Paper titled, A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations
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Topics: Central heating, Design, Engineering simulation, Nuclear fuel cycle, Simulation, Fuels, Boron, Cycles, Heating, Operating temperature
Proceedings Papers

Experimental Setup for Non-Contact Displacement Measurement of Nuclear Waste via Electromagnetic Waves

Mauro Cappelli, Vincenzo Surrenti
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A018, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16653
https://doi.org/10.1115/ICONE2020-16653
View Paper titled, Experimental Setup for Non-Contact Displacement Measurement of Nuclear Waste via Electromagnetic Waves
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Topics: Cables, Displacement measurement, Electromagnetic radiation, Radioactive wastes, Sensors, Computer simulation, Design, Electromagnetic fields, Energy consumption, Engineering prototypes
Proceedings Papers

Thermal-Hydraulic Design Support and Safety Analyses of SEALER UK Demo

Kevin Zwijsen, Heleen Uitslag-Doolaard, Ferry Roelofs, Janne Wallenius
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A028, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16526
https://doi.org/10.1115/ICONE2020-16526
View Paper titled, Thermal-Hydraulic Design Support and Safety Analyses of SEALER UK Demo
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Topics: Computational fluid dynamics, Design, Safety, Computer simulation, Energy generation, Engineering simulation, Flow (Dynamics), Freezing, Geometry, Light water reactors
Proceedings Papers

Two-Dimensional Full Core Analysis of IFBA-Coated TRISO Fuel Particles in Very High Temperature Reactors

Mohammad Alrwashdeh, Saeed A. Alameri
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T05A014, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16838
https://doi.org/10.1115/ICONE2020-16838
View Paper titled, Two-Dimensional Full Core Analysis of IFBA-Coated TRISO Fuel Particles in Very High Temperature Reactors
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Topics: Fuels, Particulate matter, Very high temperature reactors, Coating processes, Coatings, Cycles, Graphite, High temperature, Monte Carlo methods, Nuclear fuel cycle
Proceedings Papers

Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark

Junjie Rao, Xiaotong Shang, Kan Wang
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A010, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81694
https://doi.org/10.1115/ICONE26-81694
View Paper titled, Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark
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Topics: Pressure vessels, Computational methods, Neutron flux, Neutrons, Nuclear fission, Cavities, China, Neutron sources, Nuclear fuel cycle, Teams
Proceedings Papers

Preliminary Hazard Analysis of Uranium Hexafluoride Accident

Chen Lei, Zhang JianGang, Li GuoQiang, Sun ShuTang, Meng DongYuan, Wang Ning
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A030, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81956
https://doi.org/10.1115/ICONE26-81956
View Paper titled, Preliminary Hazard Analysis of Uranium Hexafluoride Accident
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Topics: Accidents, Hazard analysis, Uranium, Risk, Emergencies, Hazards, Nuclear fuel cycle
Proceedings Papers

Statistical Burnup Distribution of Moving Pebbles in HTR-PM Reactor

Fanny Vitullo, Jiri Krepel, Jarmo Kalilainen, Horst-Michael Prasser, Andreas Pautz
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A005, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81082
https://doi.org/10.1115/ICONE26-81082
View Paper titled, Statistical Burnup Distribution of Moving Pebbles in HTR-PM Reactor
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Topics: China, Construction, Cross section (Physics), Discrete element methods, Engineering simulation, Flow (Dynamics), Fuels, High temperature, Matlab, Nuclear fuel cycle
Proceedings Papers

The EUR Assessment Process and Highlights of the Compliance Analysis for the EU-APR Standard Design

Cedric Declercq, Andrew Ballard, Giovanni Ferraro, Anicet Touré
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A017, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81889
https://doi.org/10.1115/ICONE26-81889
View Paper titled, The EUR Assessment Process and Highlights of the Compliance Analysis for the EU-APR Standard Design
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Topics: Design, Nuclear power stations, Safety, Economics , Engineering disciplines, Fuels, Light water reactors, Nuclear fuel cycle, Nuclear power, Optimization
Proceedings Papers

EPR: Burnable Absorber Optimization

Michal Zeman, Radek Škoda, Jiří Závorka
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A011, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81215
https://doi.org/10.1115/ICONE26-81215
View Paper titled, EPR: Burnable Absorber Optimization
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Topics: Optimization, Fuels, European pressurized reactors, Nuclear fuel cycle, Nuclear fuels