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Proc. ASME. ICONE29, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A015, August 8–12, 2022

Paper No: ICONE29-90521

DOI: https://doi.org/10.1115/ICONE29-90521

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Topics: Cladding systems (Building), Ductility, Equipment performance, Hydrogen, Zirconium alloys, Zirconium, Accidents, Failure, Fracture (Process), Light water reactors

Proceedings Papers

Development of a Numerical Simulation Method for Air Cooling of Fuel Debris by JUPITER

Susumu Yamashita, Shinichiro Uesawa, Hiroyuki Yoshida

Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A006, August 8–12, 2022

Paper No: ICONE29-89345

DOI: https://doi.org/10.1115/ICONE29-89345

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Topics: Computer simulation, Cooling, Fuels, Natural convection, Porous materials, Temperature, Accidents, Boiling water reactors, Computational fluid dynamics, Containment vessels

Proceedings Papers

Study on Methodology for Quantification of Radioactive Discharges and Limits for Pressurized Water Reactor HPR1000 Based on Operating Experience

Yujia Chen, Weifeng Lv, Zhenyu Jiang, Yonghai Zhou

Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A024, August 8–12, 2022

Paper No: ICONE29-92385

DOI: https://doi.org/10.1115/ICONE29-92385

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Topics: Pressurized water reactors, Design, Nuclear power stations, Fluctuations (Physics), Light water reactors, Modeling, Radiation (Physics)

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

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, V001T04A009, August 4–6, 2021

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

Recent Activities and New Challenges for the EUR Organization

Vincent Sorel

Paper No: ICONE28-64617

DOI: https://doi.org/10.1115/ICONE28-64617

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Topics: Accidents, Design, Engineering standards, Fukushima nuclear disaster, Japan, 2011, Light water reactors, Nuclear power stations, Safety, Small modular reactors

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

ARKADIA – for the Innovation of Advanced Nuclear Reactor Design

Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Takashi Takata, Yasuhiro Enuma

Paper No: ICONE28-64525

DOI: https://doi.org/10.1115/ICONE28-64525

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Topics: Artificial intelligence, Computer simulation, Innovation, Nuclear design, Nuclear reactors, Optimization, Design, Safety, Carbon, Coolants

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

Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments

Fengyang Quan, Wei Li, Zikun Zhao, Xiao Zeng, Yong Guo, Yidan Yuan

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A024, August 4–6, 2021

Paper No: ICONE28-64739

DOI: https://doi.org/10.1115/ICONE28-64739

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Topics: Accidents, Cladding systems (Building), Coolants, Cooling, Dimensional analysis, Engineering prototypes, Failure, Floods, Fuels, Heat flux

Proceedings Papers

Development of Effective Momentum Model for Steam Injection Through Multi-Hole Spargers: Unit Cell Model

Xicheng Wang, Dmitry Grishchenko, Pavel Kudinov

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A084, August 4–6, 2021

Paper No: ICONE28-65751

DOI: https://doi.org/10.1115/ICONE28-65751

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Topics: Condensation, Environmental health and safety, Momentum, Steam, Thermal stratification, Turbulence, Heat, Boundary-value problems, Containment, Modeling

Proceedings Papers

Study on Collapsed Cross Section for Radial Reflector in LWR

Ryosuke Shibano, Tatsuya Kawano, Satoshi Takeda, Takanori Kitada, Yoshitada Masaoka, Hiroaki Nagano, Hideaki Hyoudo, Yasuhiro Kodama

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A079, August 4–6, 2021

Paper No: ICONE28-65686

DOI: https://doi.org/10.1115/ICONE28-65686

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Topics: Cross section (Physics), Light water reactors

Proceedings Papers

Improvement of Conversion Ratio of Thorium Fuel in LWR by Adding Neutron Absorber

Taichi Takeishi, Satoshi Takeda, Takanori Kitada

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A078, August 4–6, 2021

Paper No: ICONE28-65683

DOI: https://doi.org/10.1115/ICONE28-65683

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Topics: Fuels, Light water reactors, Neutrons

Proceedings Papers

Simulation of Severe Accident Progression Using ROSHNI: A New Integrated Simulation Code for PHWR Severe Accidents

Sunil Nijhawan, YongMann Song

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, V001T01A014, August 4–5, 2020

Paper No: ICONE2020-16633

DOI: https://doi.org/10.1115/ICONE2020-16633

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Topics: Accidents, Heavy water reactors, Simulation, Fuels, Design, Modeling, Vessels, Damage, Failure, Fluids

Proceedings Papers

Technical Maturity Assessment of Risk-Informed Safety Analysis Tools

Yong-Joon Choi

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A008, August 4–5, 2020

Paper No: ICONE2020-16700

DOI: https://doi.org/10.1115/ICONE2020-16700

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Topics: Light water reactors, Risk, Safety

Proceedings Papers

Risk-Informed Analysis for Accident Tolerant Fuel in Pressurized Water Reactors

Zhegang Ma, Carlo Parisi, Cliff Davis, Sai Zhang, Hongbin Zhang

Paper No: ICONE2020-16761

DOI: https://doi.org/10.1115/ICONE2020-16761

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Topics: Accidents, Fuels, Light water reactors, Pressurized water reactors, Risk

Proceedings Papers

Using Pipe Whip Analysis via the Finite Element Method to Underpin the Delineation Between High and Moderate Energy Lines

Antony M. Hurst, Pavitra Bansal

Paper No: ICONE2020-16474

DOI: https://doi.org/10.1115/ICONE2020-16474

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Topics: Finite element methods, Pipes, Underpinning, Hinges, Design, Finite element analysis, Light water reactors, Nuclear power stations, Nuclear reactor coolants, Stress

Proceedings Papers

Numerical Study of Tritium Mitigation Strategies for Fluoride Salt-Cooled High-Temperature Reactors

Sheng Zhang, Xiao Wu, Xiaodong Sun

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A025, August 4–5, 2020

Paper No: ICONE2020-16379

DOI: https://doi.org/10.1115/ICONE2020-16379

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Topics: Heat exchangers, High temperature, Design, Leakage, Light water reactors, Helium, Temperature, Algorithms, Coating processes, Coatings

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Multiphysics Analysis of UN Fuel Performance With a Two-Layered SiC Cladding Under Multiple Operating Conditions in a Light Water Reactor

Coupled OpenMC/CTF to VERA Core Physics Benchmark Problem 6

Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition

Development of a Numerical Simulation Method for Air Cooling of Fuel Debris by JUPITER

Study on Methodology for Quantification of Radioactive Discharges and Limits for Pressurized Water Reactor HPR1000 Based on Operating Experience

A Finnish District Heating Reactor: Background and General Overview

Recent Activities and New Challenges for the EUR Organization

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

ARKADIA – for the Innovation of Advanced Nuclear Reactor Design

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

Research on Dimensionless Analysis Method of Scale Effects for Molten Pool Experiments

Development of Effective Momentum Model for Steam Injection Through Multi-Hole Spargers: Unit Cell Model

Study on Collapsed Cross Section for Radial Reflector in LWR

Improvement of Conversion Ratio of Thorium Fuel in LWR by Adding Neutron Absorber

Simulation of Severe Accident Progression Using ROSHNI: A New Integrated Simulation Code for PHWR Severe Accidents

Technical Maturity Assessment of Risk-Informed Safety Analysis Tools

Risk-Informed Analysis for Accident Tolerant Fuel in Pressurized Water Reactors

Using Pipe Whip Analysis via the Finite Element Method to Underpin the Delineation Between High and Moderate Energy Lines

Numerical Study of Tritium Mitigation Strategies for Fluoride Salt-Cooled High-Temperature Reactors

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