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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 Dehumidification of Carbon Materials Based on Thermogravimetry

Da Yan, Kaiyue Shen, Yicheng Guo, Huaqiang Yin, Xuedong He, Tao Ma

Paper No: ICONE28-63633

DOI: https://doi.org/10.1115/ICONE28-63633

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Topics: Carbon, Dehumidification, Thermogravimetry, Very high temperature reactors, Temperature, Boron, Graphite, High temperature, Corrosion, Desorption

Proceedings Papers

A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform

Biheng Xie, Chengzhi Ji, Xiaoyu Guo, Wenbin Han, Yisheng Hao, Junyi Chen, Shanfang Huang, Kan Wang, Hongbin Wei, Yanming Liang

Paper No: ICONE28-64532

DOI: https://doi.org/10.1115/ICONE28-64532

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Topics: Simulation, Teaching, Very high temperature reactors, Accidents, Nuclear engineering, Nuclear industry, Students, Boilers, Control systems, Design

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

A Finnish District Heating Reactor: Background and General Overview

Jaakko Leppänen, Seppo Hillberg, Ville Hovi, Rebekka Komu, Joona Kurki, Unna Lauranto, Ahti Oinonen, Jussi Peltonen, Antti Rintala, Ville Tulkki, Riku Tuominen, Ville Valtavirta

Paper No: ICONE28-64346

DOI: https://doi.org/10.1115/ICONE28-64346

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Topics: Central heating, Design, Coal, Governments, Heat, Boilers, Carbon, Climate, Containment, Energy generation

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

A Sodium-Cooled Thermal-Spectrum Fission Battery

Patrick J. McDaniel, Charles Forsberg

Paper No: ICONE28-65765

DOI: https://doi.org/10.1115/ICONE28-65765

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Topics: Batteries, Nuclear fission, Sodium, Heat, Neutrons, Uranium, Carbon, Data centers, Design, Economics

Proceedings Papers

Experimental Study on Performance Improvement of HTR-10 Helium Purification System

Fangfang Wang, Liqiang Wei, Tianyu Kang, Chuangguo Hu, Feng Xie, Xiaoming Chen, Lei Shi

Paper No: ICONE28-64681

DOI: https://doi.org/10.1115/ICONE28-64681

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Topics: Copper, Helium, Particulate matter, Circuits, Desorption, Electron microscopes, Feedback, Flow (Dynamics), High temperature, Service life (Equipment)

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

Dynamic Characteristics Analysis of NuScale in Frequency Domain

Jingrui Yang, Qian Ma, Lingtong Han, Peiwei Sun

Paper No: ICONE28-64460

DOI: https://doi.org/10.1115/ICONE28-64460

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Topics: Boilers, Coolants, Design, Electric power generation, Feedwater, Flow (Dynamics), Frequency-domain analysis, Heating, Momentum, Neutrons

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

Nuclear Air-Brayton Combined Cycles Using Electrically-Heated Conductive Firebrick Heat Storage and Hydrogen for Peak Power

Charles Forsberg, Daniel Stack, Patrick McDaniel

Paper No: ICONE28-64638

DOI: https://doi.org/10.1115/ICONE28-64638

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Topics: Combined cycles, Heat storage, Hydrogen, Heat, Compressed air, High temperature, Combined cycle gas turbines, Carbon, Cycles, Energy storage

Proceedings Papers

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

Charles Forsberg

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

Experimental and Numerical Investigation on Debris Bed Quenching With Additional Injection of Non-Condensable Gas

Markus Petroff, Rudi Kulenovic, Jörg Starflinger

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A031, August 4–6, 2021

Paper No: ICONE28-65512

DOI: https://doi.org/10.1115/ICONE28-65512

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Topics: Quenching (Metalworking), Particulate matter, Accidents, Cavities, Computer simulation, Concretes, Databases, Flow (Dynamics), Gases, Light water reactors

Proceedings Papers

Development of an Integrated Design Evaluation ‘HITEP’ Platform for High-Temperature Pressure Boundary Components and Piping Systems

Hyeong-Yeon Lee, Si-Hwa Jeong, Min-Gu Won, Nam-Su Huh

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T06A004, August 4–6, 2021

Paper No: ICONE28-65552

DOI: https://doi.org/10.1115/ICONE28-65552

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Topics: Creep, Design, High temperature, Pipes, Piping systems, Pressure, Temperature

Proceedings Papers

A New Insight Into Molten Corium Concrete Interaction With Concrete Ablation Analysis for Mitigation Scheme

Ilyas Khurshid, Amidu Muritala Alade, Yacine Addad, Imran Afgan

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A028, August 4–6, 2021

Paper No: ICONE28-65217

DOI: https://doi.org/10.1115/ICONE28-65217

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Topics: Ablation (Vaporization technology), Concretes, Temperature, Underground injection

Proceedings Papers

Core Thermal-Hydraulic Analysis During Dipped-Type Direct Heat Exchanger Operation in Natural Circulation Conditions

Erina Hamase, Norihiro Doda, Ayako Ono, Masaaki Tanaka, Yasuhiro Miyake, Yasutomo Imai

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A005, August 4–6, 2021

Paper No: ICONE28-63380

DOI: https://doi.org/10.1115/ICONE28-63380

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Topics: Computational fluid dynamics, Flow (Dynamics), Heat exchangers, Sodium fast reactors, Fuels, Reactor vessels, Sodium, Coolants, Cooling, Cooling systems

Proceedings Papers

The Evaluation of Break Sizes of LOCA by the Temperature Difference at the Recirculation Inlets of BWR

Sheng-Dih Hwang

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A029, August 4–6, 2021

Paper No: ICONE28-65413

DOI: https://doi.org/10.1115/ICONE28-65413

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Topics: Boiling water reactors, Temperature, Accidents, Control rooms, Engineering simulation, Nuclear reactors, Probability, Simulation

Proceedings Papers

Investigation on Solidification Behavior of Deposited Metal by GTAW With ERNiCrFe-13 Wire

Xiao Guo, Kai Xu, Xiaochun Lv, Peiyin Chen, Bo Chen, Shubin Huo

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, V003T10A001, August 4–6, 2021

Paper No: ICONE28-63770

DOI: https://doi.org/10.1115/ICONE28-63770

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Topics: Gas tungsten arc welding, Metals, Solidification, Wire, Temperature, Cracking (Materials), Fracture (Process), Differential scanning calorimetry, Ductility, Lasers

Proceedings Papers

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

Yubin Zhang

Paper No: ICONE28-64737

DOI: https://doi.org/10.1115/ICONE28-64737

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Topics: Numerical analysis, Reactor vessels, Thermal shock, Accidents, Computational fluid dynamics, Computer software, Coolants, Flow (Dynamics), Mechanical structures, Nozzles

2 3 4 5

NARROW

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

Study on Dehumidification of Carbon Materials Based on Thermogravimetry

A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform

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

A Finnish District Heating Reactor: Background and General Overview

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

A Sodium-Cooled Thermal-Spectrum Fission Battery

Experimental Study on Performance Improvement of HTR-10 Helium Purification System

Sensitivity Study on TRISO Fuel Failure Probability Evaluation for HTGR

Dynamic Characteristics Analysis of NuScale in Frequency Domain

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

Nuclear Air-Brayton Combined Cycles Using Electrically-Heated Conductive Firebrick Heat Storage and Hydrogen for Peak Power

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

Experimental and Numerical Investigation on Debris Bed Quenching With Additional Injection of Non-Condensable Gas

Development of an Integrated Design Evaluation ‘HITEP’ Platform for High-Temperature Pressure Boundary Components and Piping Systems

A New Insight Into Molten Corium Concrete Interaction With Concrete Ablation Analysis for Mitigation Scheme

Core Thermal-Hydraulic Analysis During Dipped-Type Direct Heat Exchanger Operation in Natural Circulation Conditions

The Evaluation of Break Sizes of LOCA by the Temperature Difference at the Recirculation Inlets of BWR

Investigation on Solidification Behavior of Deposited Metal by GTAW With ERNiCrFe-13 Wire

Numerical Analysis of Pressurized Thermal Shock in Reactor Pressure Vessel

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