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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
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Topics: Dislocations, Iron, Molecular dynamics, Steel
Proceedings Papers

100-Gigawatt-Hour Crushed-Rock Heat Storage for Variable Electricity and Heat With Base-Load Reactor Operations

Charles Forsberg
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, V001T02A027, August 4–6, 2021
Paper No: ICONE28-64632
DOI: https://doi.org/10.1115/ICONE28-64632
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Topics: Heat, Heat storage, Rocks, Stress, Storage, Fluids, Heat transfer, Plasma spraying, Spraying (Coating processes), Dimensions
Proceedings Papers

Sensitivity Analysis on the Blast Resistance of Steel Concrete Structure Wall Based on CONWEP

Guopeng Ren, Rong Pan, Feng Sun, Liang 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, V003T12A022, August 4–6, 2021
Paper No: ICONE28-64415
DOI: https://doi.org/10.1115/ICONE28-64415
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Topics: Concretes, Sensitivity analysis, Steel
Proceedings Papers

Investigation and Design of Energy-Absorbing Structure in Nuclear Fuel Cask

Yuchen Hao, Yue Li, Jinhua Wang, Bin Wu, Tao Ma, Haitao Wang
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, V003T11A007, August 4–6, 2021
Paper No: ICONE28-63388
DOI: https://doi.org/10.1115/ICONE28-63388
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Topics: Design, Nuclear fuels, Transportation systems, Fuels, Metals, Safety, High temperature, Construction, Containers, Economics
Proceedings Papers

FUELPOOL: A Computer Program to Model CANDU Spent Fuel Pool Severe Accident Progression and Consequences

Yong Mann Song, Jong Yeob Jung, Sunil Nijhawan
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, V001T01A015, August 4–5, 2020
Paper No: ICONE2020-16634
DOI: https://doi.org/10.1115/ICONE2020-16634
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Topics: Accidents, Computer software, Spent nuclear fuels, Fuels, Fluids, Heavy water reactors, Radiation (Physics), Stainless steel, Steel, Water
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Kinetic Study of Boron Carbide-Stainless Steel Eutectic Melting by Differential Thermal Analysis

Shin Kikuchi, Hidemasa Yamano, Kinya Nakamura
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A004, August 4–5, 2020
Paper No: ICONE2020-16075
DOI: https://doi.org/10.1115/ICONE2020-16075
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Topics: Accidents, Boron, Melting, Sodium fast reactors, Steel, Thermal analysis
Proceedings Papers

Heating Impact on Corrosion Mechanism of Carbon Steel Surrounded by Bentonite

Masao Uyama, Hiroyuki Saito, Tomoya Iioka
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A056, August 4–5, 2020
Paper No: ICONE2020-16765
DOI: https://doi.org/10.1115/ICONE2020-16765
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Topics: Carbon steel, Corrosion, Electrochemical impedance spectroscopy, Heating, Radioactive wastes, Steel
Proceedings Papers

Study on Irradiation Damage of RPV Steels Based on Coupling Cluster Dynamics and Crystal Plasticity Finite Element Method

Xiaotong Wang, Ying Luo, Yuanyuan Dong, Weihua Yao
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A017, August 4–5, 2020
Paper No: ICONE2020-16272
DOI: https://doi.org/10.1115/ICONE2020-16272
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Topics: Crystals, Damage, Dynamics (Mechanics), Finite element methods, Irradiation (Radiation exposure), Plasticity, Reactor vessels, Steel
Proceedings Papers

Irradiation Induced Crosslinking in “Green” Polylactic-Acid (PLA) Polymers for Enhanced Strength and Elevated Temperature Applications

W. Jiang, A. Bakken, R. P. Taleyarkhan
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A044, August 4–5, 2020
Paper No: ICONE2020-16767
DOI: https://doi.org/10.1115/ICONE2020-16767
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Topics: Adhesives, Irradiation (Radiation exposure), Polymers, Temperature, Photons, Testing, Accidents, Bond strength, Bonding, Construction
Proceedings Papers

Severe Accident Analysis for Reactor Core Applying SiC to Fuel Claddings and Channel Boxes

Hideki Horie, Yutaka Takeuchi, Kenya Takiwaki, Fumie Sebe, Kazuo Kakiuchi, Hisaki Sato
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A034, July 22–26, 2018
Paper No: ICONE26-81923
DOI: https://doi.org/10.1115/ICONE26-81923
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Topics: Accidents, Fuels, Oxidation, Cladding systems (Building), High temperature, Hydrogen, Nuclear power stations, Temperature, Chemical reactions, Damage
Proceedings Papers

Rewetting Analysis of Hot Moving Surface by Round Water Jet Impingement

Avadhesh Kumar Sharma, Mayank Modak, Santosh K. Sahu
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A043, July 22–26, 2018
Paper No: ICONE26-81673
DOI: https://doi.org/10.1115/ICONE26-81673
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Topics: Cooling, Hot rolling, Imaging, Jets, Manufacturing industry, Nozzles, Quenching (Metalworking), Reynolds number, Stainless steel, Steel
Proceedings Papers

A Recommended Method for SC Wall Design-Evaluation Regarding the Elasto-Plastic Behavior Under Beyond Design Basis Seismic Loading

Ziduan Shang, Xiao Huang, Yugang Sun, Meng Chu
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A003, July 22–26, 2018
Paper No: ICONE26-81088
DOI: https://doi.org/10.1115/ICONE26-81088
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Topics: Design, Composite materials, Concretes, Steel, Constitutive equations, Shear (Mechanics), Construction, Nuclear power stations, Plates (structures), Stress
Proceedings Papers

Radiation Protection Calculation and Optimization for Shielding Design Around the Refueling Pipelines of HTR-PM

Sheng Fang, Hong Li, Wenqian Li
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A024, July 22–26, 2018
Paper No: ICONE26-82581
DOI: https://doi.org/10.1115/ICONE26-82581
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Topics: Design, Optimization, Pipelines, Radiation (Physics), Fuels, Steel, Cables, China, Concrete walls, Cycles
Proceedings Papers

Development of a Crack Opening Displacement Assessment Procedure Considering Change of Compliance at a Crack Part in Thin Wall Pipes Made of Modified 9Cr-1Mo Steel

Takashi Wakai, Hideo Machida, Manabu Arakawa, Seiji Yanagihara, Ryosuke Suzuki, Masaaki Matsubara
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A035, July 22–26, 2018
Paper No: ICONE26-82619
DOI: https://doi.org/10.1115/ICONE26-82619
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Topics: Displacement, Fracture (Materials), Pipes, Steel, Thin wall structures, Leakage, Sodium fast reactors, Sodium, Work hardening, Coolants
Proceedings Papers

Study on Control Strategy of Hydrogen Risk in Small Containment Under Severe Accident

Zou Zhiqiang, Zhang Ming, Peng Huanhuan, Hou Liqiang, Deng Chunrui, Qiao Xuedong
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A008, July 22–26, 2018
Paper No: ICONE26-81899
DOI: https://doi.org/10.1115/ICONE26-81899
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Topics: Accidents, Containment, Hydrogen, Risk, Oxygen, Steam, Steel, Combustion, Condensation, Cooling systems
Proceedings Papers

A Revised Methodology to Assess In-Vessel Retention Strategy for High-Power Reactors

F. Fichot, L. Carénini, W. Villanueva, S. Bechta
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A014, July 22–26, 2018
Paper No: ICONE26-82248
DOI: https://doi.org/10.1115/ICONE26-82248
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Topics: Vessels, Safety, Transients (Dynamics), Flux (Metallurgy), Heat, Metals, Light water reactors, Critical heat flux, Heat flux, Steady state
Proceedings Papers

Numerical Simulation of Debris Bed Relocation Behavior in Sodium-Cooled Fast Reactor

Chunming Teng, Bin Zhang, Jianqiang Shan
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A044, July 22–26, 2018
Paper No: ICONE26-82493
DOI: https://doi.org/10.1115/ICONE26-82493
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Topics: Computer simulation, Sodium fast reactors, Particulate matter, Shear strength, Fuels, Accidents, Boiling, Coolants, Cooling, Density
Proceedings Papers

Facilities and Experience on Impact Test of Packages for Radioactive Materials Transport

Li Guoqiang, Zhuang Dajie, Wang Xuexin, Meng Dongyuan, Zhang Jiangang, Sun Hongchao, Sun Shutang, Ma Anping
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A016, July 22–26, 2018
Paper No: ICONE26-81451
DOI: https://doi.org/10.1115/ICONE26-81451
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Topics: Impact testing, Radioactive substances, Reinforced concrete, Steel, Accidents, Concretes, Construction, Cranes, Measuring instruments, Stress
Proceedings Papers

A Concept of Intermediate Heat Exchanger for High-Temperature Gas Reactor Hydrogen and Power Cogeneration System

Noriaki Hirota, Atsuhiko Terada, Xing L. Yan, Kohei Tanaka, Akihito Otani
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A015, July 22–26, 2018
Paper No: ICONE26-81718
DOI: https://doi.org/10.1115/ICONE26-81718
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Topics: Combined heat and power, Heat exchangers, High temperature, Hydrogen, Nuclear reactors, Conceptual design, Design, Gas turbines, Construction, Creep
Proceedings Papers

Replacement of a Hot Cell Window at the Hot Fuel Examination Facility

Judith Carol Westphal, Ron Johansen, J. D. Kelly
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T01A017, July 22–26, 2018
Paper No: ICONE26-82422
DOI: https://doi.org/10.1115/ICONE26-82422
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Topics: Fuels, Slabs, Leakage, Glass, Gaskets, Mineral oil, Design, Dust, Flanges, Adhesion