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Proceedings Papers

Feasibility Study of Disassembly Technologies of Fast Reactor Fuel Assembly

Hidetsugu Nishikawa, Masayuki Takeuchi, Toru Kitagaki, Yuuichi Tooya
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A010, August 4–6, 2021
Paper No: ICONE28-64250
DOI: https://doi.org/10.1115/ICONE28-64250
View Paper titled, Feasibility Study of Disassembly Technologies of Fast Reactor Fuel Assembly
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Topics: Cutting, Fast neutron reactors, Fuels, Manufacturing, Wheels
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
Paper No: ICONE28-64210
DOI: 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

Levelized Cost of Electricity Evaluation Methodology Applied to High-Burnup 18 and 24-Month Fuel Cycles

David L. Stucker, Jeff Norrell, Ho Lam, Fausto Franceschini
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A019, August 4–6, 2021
Paper No: ICONE28-66589
DOI: https://doi.org/10.1115/ICONE28-66589
View Paper titled, Levelized Cost of Electricity Evaluation Methodology Applied to High-Burnup 18 and 24-Month Fuel Cycles
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Topics: Cycles, Fuel management, Fuels, Uranium
Proceedings Papers

A Statistical Approach for Modeling the Effect of Hot Press Conditions on the Mechanical Strength Properties of HTGR Fuel Elements

Aihara Jun, Kuroda Masatoshi, Tachibana Yukio
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A011, August 4–6, 2021
Paper No: ICONE28-64507
DOI: https://doi.org/10.1115/ICONE28-64507
View Paper titled, A Statistical Approach for Modeling the Effect of Hot Press Conditions on the Mechanical Strength Properties of HTGR Fuel Elements
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Topics: Fuels, Modeling, Strength (Materials), Very high temperature reactors, Carbon, Design, Experimental design, Oxidation, Pressure, Response surface methodology
Proceedings Papers

Development of Cesium Trap Material for Coated Fuel Particles in High Temperature Gas-Cooled Reactors

K. Sasaki, S. Miura, K. Fukumoto, M. Goto, H. Ohashi
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A002, August 4–6, 2021
Paper No: ICONE28-61765
DOI: https://doi.org/10.1115/ICONE28-61765
View Paper titled, Development of Cesium Trap Material for Coated Fuel Particles in High Temperature Gas-Cooled Reactors
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Topics: Fuels, Particulate matter, Very high temperature reactors
Proceedings Papers

Experimental Study on Edge Blockage Accidents in a Narrow Rectangular Channel

Dongdong Yuan, Weian Du, Yuhao He, Jiahong Zhu, Yonghao Zhang, Chengwei Li, Sichao Tan, Dongyang Li
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A012, August 4–6, 2021
Paper No: ICONE28-64684
DOI: https://doi.org/10.1115/ICONE28-64684
View Paper titled, Experimental Study on Edge Blockage Accidents in a Narrow Rectangular Channel
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Topics: Accidents, Fuels, Manufacturing
Proceedings Papers

Evaluation of Interface Stresses and Cladding-Cladding Delamination Failures In U-Mo Fuel Plates

Hakan Ozaltun
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A018, August 4–6, 2021
Paper No: ICONE28-65840
DOI: https://doi.org/10.1115/ICONE28-65840
View Paper titled, Evaluation of Interface Stresses and Cladding-Cladding Delamination Failures In U-Mo Fuel Plates
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Topics: Cladding systems (Building), Delamination, Failure, Failure mechanisms, Fuels, Plates (structures), Stress
Proceedings Papers

Preliminary Research on The Thermal-Mechanical Coupling Behavior Simulation Method of M3 Fuel

Tang Changbing, Jiao Yongjun, Li Yuanming, Zhang Kun
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A013, August 4–6, 2021
Paper No: ICONE28-64920
DOI: https://doi.org/10.1115/ICONE28-64920
View Paper titled, Preliminary Research on The Thermal-Mechanical Coupling Behavior Simulation Method of M3 Fuel
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Topics: Fuels, Simulation
Proceedings Papers

Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR

Jian Li, Ding She, Lei Shi
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A008, August 4–6, 2021
Paper No: ICONE28-64154
DOI: https://doi.org/10.1115/ICONE28-64154
View Paper titled, Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR
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Topics: Failure, Fuels, Probability, Very high temperature reactors, Irradiation (Radiation exposure), Particulate matter, Stress, Materials properties, Temperature, Anisotropy
Proceedings Papers

Evaluation of the Applicability of Plutonium Transmuted From Minor Actinides by Fusion Reactor as Fertile Fuel in Boiling Water Reactor

Masaki Shimizu, Hiroki Shishido, Hidetoshi Hashizume
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A014, August 4–6, 2021
Paper No: ICONE28-65139
DOI: https://doi.org/10.1115/ICONE28-65139
View Paper titled, Evaluation of the Applicability of Plutonium Transmuted From Minor Actinides by Fusion Reactor as Fertile Fuel in Boiling Water Reactor
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Topics: Boiling water reactors, Fuels, Fusion reactors, Light water reactors
Proceedings Papers

Flow Induced Vibration and Fretting Wear Characteristics of Fuel Rods

Zhipeng Feng, Huanhuan Qi, Xuan Huang, Guo Chen, Shuai Liu, Yixiong Zhang
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A003, August 4–6, 2021
Paper No: ICONE28-62135
DOI: https://doi.org/10.1115/ICONE28-62135
View Paper titled, Flow Induced Vibration and Fretting Wear Characteristics of Fuel Rods
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Topics: Flow-induced vibrations, Fuel rods, Wear, Fuels, Manufacturing, Design, Fluid density, Pressurized water reactors, Evaluation methods, Excitation
Proceedings Papers

Atomic Insights on Interaction Mechanism of Dislocation With Void/Impurity/Precipitates in BCC Iron

M. Mustafa Azeem, Di Yun, Muhammad Zubair
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A015, August 4–6, 2021
Paper No: ICONE28-65197
DOI: https://doi.org/10.1115/ICONE28-65197
View Paper titled, Atomic Insights on Interaction Mechanism of Dislocation With Void/Impurity/Precipitates in BCC Iron
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Topics: Dislocations, Iron, Molecular dynamics, Steel
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
Paper No: ICONE28-63354
DOI: 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

Modeling of Irradiation-Induced Thermo-Mechanical Coupling Behavior in Metal Matrix Microencapsulated Fuel

Hongyang Wei, Fawen Zhu, Jun Ru, Haoyu Wang, Jing Zhang, Hua Li, Yun Li, Chunlan Huang, Yuanming Li, Shurong Ding
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A016, August 4–6, 2021
Paper No: ICONE28-65563
DOI: https://doi.org/10.1115/ICONE28-65563
View Paper titled, Modeling of Irradiation-Induced Thermo-Mechanical Coupling Behavior in Metal Matrix Microencapsulated Fuel
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Topics: Finite element analysis, Fuels, Irradiation (Radiation exposure), Metals, Modeling, Thermomechanics
Proceedings Papers

Manufacturability Estimation on Burnable Poison Mixed Fuel For Improving Criticality Safety of HTGR Fuel Fabrication

Toshinari Hasegawa, Yuji Fukaya, Shohei Ueta, Minoru Goto
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A001, August 4–6, 2021
Paper No: ICONE28-61763
DOI: https://doi.org/10.1115/ICONE28-61763
View Paper titled, Manufacturability Estimation on Burnable Poison Mixed Fuel For Improving Criticality Safety of HTGR Fuel Fabrication
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Topics: Fuels, Manufacturing, Safety, Very high temperature reactors
Proceedings Papers

Research on Application of Additive Manufacturing Technology In Nuclear Fuel Assembly Field

Hua Li, Ti Yue, Fawen Zhu, Yuan Peng, Yun Li, Chunlan Huang, Youjia Zhang
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A017, August 4–6, 2021
Paper No: ICONE28-65776
DOI: https://doi.org/10.1115/ICONE28-65776
View Paper titled, Research on Application of Additive Manufacturing Technology In Nuclear Fuel Assembly Field
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Topics: Additive manufacturing, Design, Fuels, Manufacturing, Nuclear fuels
Proceedings Papers

Steady-State Performance Analysis of a Dual-Cladding Design for Accident Tolerance Fuel

Qianliang Deng, Songyang Li, Dingqu Wang, Yueyuan Jiang, Zhihong Liu, Wei Xiong, Yalin Tian
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A004, August 4–6, 2021
Paper No: ICONE28-63101
DOI: https://doi.org/10.1115/ICONE28-63101
View Paper titled, Steady-State Performance Analysis of a Dual-Cladding Design for Accident Tolerance Fuel
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Topics: Accidents, Cladding systems (Building), Design, Fuels, Steady state
Proceedings Papers

Risk Analysis of Gasification Process of Nuclear Fuel Manufacturing Facilities Based on FTA

Xiaowei Yang, Dan Lyu, Ji Que, Yuntao Liu, Shangui Zhao
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A006, August 4–6, 2021
Paper No: ICONE28-63648
DOI: https://doi.org/10.1115/ICONE28-63648
View Paper titled, Risk Analysis of Gasification Process of Nuclear Fuel Manufacturing Facilities Based on FTA
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Topics: Fuel gasification, Nuclear fuels, Production facilities, Risk analysis
Proceedings Papers

Prediction of Iodine Peak and Iodine Purification Time in PWR Nuclear Power Plant With Defective Fuel Rods

Liang Wang, Zhiyuan Liu, Fei Liu, Chunming Zhang, Fudong Liu, Yuanlv Ye
Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A007, August 4–6, 2021
Paper No: ICONE28-64147
DOI: https://doi.org/10.1115/ICONE28-64147
View Paper titled, Prediction of Iodine Peak and Iodine Purification Time in PWR Nuclear Power Plant With Defective Fuel Rods
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Topics: Failure, Fuel rods, Nuclear power stations, Pressurized water reactors, Radiation (Physics), Safety