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Proceedings Papers

Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor

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, V001T04A014, August 4–6, 2021

Paper No: ICONE28-65689

DOI: https://doi.org/10.1115/ICONE28-65689

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Topics: Isotopes, Neutrons, Optimization, Physics, Small modular reactors, Temperature, Cycles, Design, Fuels, China

Proceedings Papers

Study on the Transport Mechanism and Troubleshooting Analysis of Spherical Fuel in High Temperature Gas Cooled Reactor

Jinhua Wang, Yuchen Hao, Yue Li, Bin Wu, Haitao Wang, Tao Ma

Paper No: ICONE28-63134

DOI: https://doi.org/10.1115/ICONE28-63134

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Topics: Fuels, Gas cooled reactors, High temperature, Nuclear power, Transportation systems

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

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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

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Topics: Failure, Fuels, Radioisotopes, Chain, Cladding systems (Building), Coolants, Corrosion, Damage, Fracture (Materials), Manufacturing

Proceedings Papers

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

Jaakko Leppänen, Ville Valtavirta, Riku Tuominen, Antti Rintala, Unna Lauranto

Paper No: ICONE28-64347

DOI: https://doi.org/10.1115/ICONE28-64347

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Topics: Central heating, Design, Engineering simulation, Nuclear fuel cycle, Simulation, Fuels, Boron, Cycles, Heating, Operating temperature

Proceedings Papers

Numerical Study on Multiscale Heat Conduction Problems in Very High Temperature Reactor Fuel Pebble Based on OpenFOAM

Jincheng Wang, Ming Ding

Paper No: ICONE28-64416

DOI: https://doi.org/10.1115/ICONE28-64416

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Topics: Fuels, Heat conduction, Very high temperature reactors

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

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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

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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

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Topics: Fuels, Particulate matter, Very high temperature reactors

Proceedings Papers

UHT Test Facility Updates and Oxidation Tests for Accident Tolerant Fuel Development

William A. Byers, Guoqiang Wang

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A042, August 4–6, 2021

Paper No: ICONE28-66592

DOI: https://doi.org/10.1115/ICONE28-66592

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Topics: Accidents, Fuels, High temperature, Oxidation, Test facilities, Zirconium alloys

Proceedings Papers

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Guoqiang Wang, William A. Byers, Zeses Karoutas

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A041, August 4–6, 2021

Paper No: ICONE28-66591

DOI: https://doi.org/10.1115/ICONE28-66591

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Topics: Accidents, Cladding systems (Building), Critical heat flux, Fuels, Chemistry, Pressurized water reactors, Coolants, Electrical resistivity, Film boiling, Heat flux

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

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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

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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

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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

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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

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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

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Topics: Flow-induced vibrations, Fuel rods, Wear, Fuels, Manufacturing, Design, Fluid density, Pressurized water reactors, Evaluation methods, Excitation

Proceedings Papers

Study on the Small Pressurized Water Reactor Based on Fully Ceramic Microencapsulated Fuel

Jin Feng Huang

Paper No: ICONE28-63314

DOI: https://doi.org/10.1115/ICONE28-63314

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Topics: Ceramics, Fuels, Pressurized water reactors, Cladding systems (Building), Cycles, Nuclear power stations, Silicon, Temperature, Thermal conductivity, Boron

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

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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

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Topics: Fuels, Manufacturing, Safety, Very high temperature reactors

2 3 4 5

NARROW

Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor

Study on the Transport Mechanism and Troubleshooting Analysis of Spherical Fuel in High Temperature Gas Cooled Reactor

Feasibility Study of Disassembly Technologies of Fast Reactor Fuel Assembly

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

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

Numerical Study on Multiscale Heat Conduction Problems in Very High Temperature Reactor Fuel Pebble Based on OpenFOAM

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

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

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

UHT Test Facility Updates and Oxidation Tests for Accident Tolerant Fuel Development

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Experimental Study on Edge Blockage Accidents in a Narrow Rectangular Channel

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

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

Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR

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

Flow Induced Vibration and Fretting Wear Characteristics of Fuel Rods

Study on the Small Pressurized Water Reactor Based on Fully Ceramic Microencapsulated Fuel

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

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

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