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Proceedings Papers

Implementation Challenges and Proposed Suggestions for Nuclear Material Accountancy Management in Spent Fuel Reprocessing Plant

Lixia He, Lei Bai, Qiang Miao, Qun Yang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A019, August 8–12, 2022

Paper No: ICONE29-91491

DOI: https://doi.org/10.1115/ICONE29-91491

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Topics: Accounting, Spent nuclear fuels

Proceedings Papers

Research Status of Spent Fuel Transport Containers

Changwu Wang, Zhipeng Wang, Qian Sun, Yuhang Zhang

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A063, August 8–12, 2022

Paper No: ICONE29-93580

DOI: https://doi.org/10.1115/ICONE29-93580

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Topics: Computer simulation, Containers, Design, Spent nuclear fuels

Proceedings Papers

Scaling of Thermal and Flow Behavior in Dry Storage Casks for Nuclear Spent Fuel

Qinglong Wen, Ting Yang, Shijia Xu, Zhengquan Wang, Bo Yuan

Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A016, August 8–12, 2022

Paper No: ICONE29-89444

DOI: https://doi.org/10.1115/ICONE29-89444

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Topics: Flow (Dynamics), Spent nuclear fuels, Storage

Proceedings Papers

Study on Probabilistic Safety Analysis Method of Spent Fuel Reprocessing Facilities

Jinghan Zhang, Jun Zhao, Jie Hou

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A013, August 8–12, 2022

Paper No: ICONE29-90767

DOI: https://doi.org/10.1115/ICONE29-90767

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Topics: Probabilistic safety assessment, Spent nuclear fuels

Proceedings Papers

PSA Application for UK HPR1000 ALARP Demonstration

Zhiwen Wang, Chunju Yang, Bing Zhang, Jinkai Wang, Huina Sang, Lingmei Xiao, Fei Wang, Ming Wang

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A043, August 8–12, 2022

Paper No: ICONE29-93109

DOI: https://doi.org/10.1115/ICONE29-93109

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Topics: China, Design, Fire, Floods, Hazards, Nuclear power, Probabilistic safety assessment, Risk, Safety, Spent nuclear fuels

Proceedings Papers

Spent Fuel Pool Risk Analysis for a CPR1000 Unit

Liu Weidong, Liu Leilei

Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A028, August 8–12, 2022

Paper No: ICONE29-91949

DOI: https://doi.org/10.1115/ICONE29-91949

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Topics: Damage, Fuels, Probabilistic safety assessment, Risk analysis, Spent nuclear fuels

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

Paper No: ICONE29-91659

DOI: https://doi.org/10.1115/ICONE29-91659

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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

Paper No: ICONE29-90873

DOI: https://doi.org/10.1115/ICONE29-90873

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Topics: Chemical reactions, Nuclear power, Nuclides, Computer software, Bonding, Chemical properties, Chemistry, Desorption, Diffusion processes, Equilibrium (Physics)

Proceedings Papers

The Study of Removal of Secondary Neutron Source of HPR-1000

Huiwen Xiao, Xiang Li, Guoming Liu, Yicheng Zhang, Zeng Shao, Min Xu, Xuan Yi, Haifeng Yang

Proc. ASME. ICONE29, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A061, August 8–12, 2022

Paper No: ICONE29-93024

DOI: https://doi.org/10.1115/ICONE29-93024

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Topics: Neutron sources, Spent nuclear fuels

Proceedings Papers

PWR Spent Fuel Dry Storage Loading Pattern and Safety Evaluation

Li Wen, Gao Jinghui, Li Gang, Zhong Shengdong, Xu Jin, Zhao Bingquan

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A078, August 8–12, 2022

Paper No: ICONE29-93351

DOI: https://doi.org/10.1115/ICONE29-93351

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Topics: Pressurized water reactors, Safety, Spent nuclear fuels, Storage

Proceedings Papers

Study on Risk of Nuclear Spent Fuel Marine Transportation

Liu Yiqing, Wang Wei, Zhao Xiaodong, Gui Zhong, Chen Jiangtao

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A067, August 8–12, 2022

Paper No: ICONE29-92870

DOI: https://doi.org/10.1115/ICONE29-92870

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Topics: Marine transportation, Risk, Risk analysis, Spent nuclear fuels

Proceedings Papers

Interpretation and Analysis of Design Idea of the Spent Fuel Transport Ship

Gui Zhong, Zhang Hui, Wang Wei, Yuan Yueyan, Liu Chao, Li Xiaoqing

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A065, August 8–12, 2022

Paper No: ICONE29-92809

DOI: https://doi.org/10.1115/ICONE29-92809

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Topics: Design, Safety, Ships, Spent nuclear fuels

Proceedings Papers

Development and Experiment on High Temperature and Radiation Resistance Concrete Material for Spent Fuel Dry Storage

Zhang Xueling, Cheng Cheng, Pan Yongjie, Wei Yuanyuan, Tang Qionghui, Li Zengfen, Yang Shouhai

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A047, August 8–12, 2022

Paper No: ICONE29-92125

DOI: https://doi.org/10.1115/ICONE29-92125

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Topics: Concretes, Fibers, High temperature, Radiation (Physics), Spent nuclear fuels, Steel, Storage, Tension

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

Paper No: ICONE29-89241

DOI: https://doi.org/10.1115/ICONE29-89241

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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

Thermal Experimental and Analysis of Vertical Spent Fuel Dry Storage Canister

Qionghui Tang, Mao-Yun Li, Cheng Cheng, En-Fei Xie

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A051, August 8–12, 2022

Paper No: ICONE29-92217

DOI: https://doi.org/10.1115/ICONE29-92217

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Topics: Computational fluid dynamics, Spent nuclear fuels, Storage

Proceedings Papers

Extraction of Nd(III), Eu(III), Am(III) and Cm(III) With 6-Carboxylic Di(2-Ethylhexyl) Amide Pyridine

Chao Xu, Yu Du, Tingting Liu, Suliang Yang

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A024, August 8–12, 2022

Paper No: ICONE29-90818

DOI: https://doi.org/10.1115/ICONE29-90818

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Topics: Atoms, Cycles, Design, Equilibrium (Physics), Infrared spectra, Ion exchange, Mass transfer, Separation (Technology), Spent nuclear fuels, Temperature

Proceedings Papers

Drop Analyses and Verification of the Spent Nuclear Fuel Transportation Cask Under Hypothetical Accident Conditions

Guangdong Liu, Weiliang Wu, He Zhu, Qingjun Ma, Qipeng Li

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A042, August 8–12, 2022

Paper No: ICONE29-91927

DOI: https://doi.org/10.1115/ICONE29-91927

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Topics: Accidents, Spent nuclear fuels, Stress, Transportation systems

Proceedings Papers

Neutronics Analysis of RBMK-1000 Reactor Using OpenMC: Criticality and Depletion Analysis at 3D Assembly Level

Mohammad Hashemi, Rafael Macián-Juan, Martin Ohlerich

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A018, August 8–12, 2022

Paper No: ICONE29-90636

DOI: https://doi.org/10.1115/ICONE29-90636

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Topics: Manufacturing, Nuclear fission, Spent nuclear fuels, Chemical kinetics, Computer programming languages, Databases, Design, Nuclear power, Nuclear power stations, Parametric design

Proceedings Papers

Study on the Policy and Legislative System of Spent Nuclear Fuel Management in Different Developed Countries

Lei Shi, Chao Chen, Hongjun Liu, Jiqiang Su, Honglin Zhang, Qun Liu, Yanrui Li, Jian Hu

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A069, August 8–12, 2022

Paper No: ICONE29-92948

DOI: https://doi.org/10.1115/ICONE29-92948

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Topics: Spent nuclear fuels

Proceedings Papers

Development and Application of High Temperature and Radiation Protection Equipment for Spent Fuel Dry Storage System

Cheng Cheng, Wei Yuanyuan, Pan Yongjie, Ge Yongjun, Wei Zhiguo, Zhou Zhihui, Li Zengfen

Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A045, August 8–12, 2022

Paper No: ICONE29-92083

DOI: https://doi.org/10.1115/ICONE29-92083

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Topics: High temperature, Radiation (Physics), Risk, Spent nuclear fuels, Storage

NARROW

Implementation Challenges and Proposed Suggestions for Nuclear Material Accountancy Management in Spent Fuel Reprocessing Plant

Research Status of Spent Fuel Transport Containers

Scaling of Thermal and Flow Behavior in Dry Storage Casks for Nuclear Spent Fuel

Study on Probabilistic Safety Analysis Method of Spent Fuel Reprocessing Facilities

PSA Application for UK HPR1000 ALARP Demonstration

Spent Fuel Pool Risk Analysis for a CPR1000 Unit

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

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

The Study of Removal of Secondary Neutron Source of HPR-1000

PWR Spent Fuel Dry Storage Loading Pattern and Safety Evaluation

Study on Risk of Nuclear Spent Fuel Marine Transportation

Interpretation and Analysis of Design Idea of the Spent Fuel Transport Ship

Development and Experiment on High Temperature and Radiation Resistance Concrete Material for Spent Fuel Dry Storage

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

Thermal Experimental and Analysis of Vertical Spent Fuel Dry Storage Canister

Extraction of Nd(III), Eu(III), Am(III) and Cm(III) With 6-Carboxylic Di(2-Ethylhexyl) Amide Pyridine

Drop Analyses and Verification of the Spent Nuclear Fuel Transportation Cask Under Hypothetical Accident Conditions

Neutronics Analysis of RBMK-1000 Reactor Using OpenMC: Criticality and Depletion Analysis at 3D Assembly Level

Study on the Policy and Legislative System of Spent Nuclear Fuel Management in Different Developed Countries

Development and Application of High Temperature and Radiation Protection Equipment for Spent Fuel Dry Storage System

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