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Proceedings Papers

Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation

Shuowang Fan, Yutong Chen, Dalin Zhang, Xiaoli Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su
Proc. ASME. ICONE31, Volume 6: Thermal-Hydraulics and Safety Analysis, V006T07A045, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134796
https://doi.org/10.1115/ICONE31-134796
View Paper titled, Numerical Study on Molten Stainless Steel and Lead Bismuth Eutectic Interaction for Lead-Cooled Fast Reactors Using the ACENA Code With Experimental Validation
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Topics: Fast neutron reactors, Stainless steel, Coolants, Temperature, Accidents, Pressure, Safety, Sodium, Temperature distribution, Vessels
Proceedings Papers

Development of a New Crust Model for Analyzing VULCANO VBS-U3 MCCI Experiment With MPS Method

Takeshi Yamada, Xin Li, Takuya Yamashita, Akifumi Yamaji
Proc. ASME. ICONE31, Volume 7: Computational Fluid Dynamics (CFD) and Applications, V007T08A007, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134499
https://doi.org/10.1115/ICONE31-134499
View Paper titled, Development of a New Crust Model for Analyzing VULCANO VBS-U3 MCCI Experiment With MPS Method
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Topics: Ablation (Vaporization technology), Accidents, Chaos, Computation, Computational fluid dynamics, Computer simulation, Concrete walls, Concretes, Containment, Displacement
Proceedings Papers

Simulation on the Process of Core Molten Pool Formation and Corium Relocation in the Core Region

Xinhai Zhao, Peng Chen, Dongyu He, Ruhao Zhong
Proc. ASME. ICONE29, Volume 11: Mitigation Strategies for Beyond Design Basis Events, V011T11A017, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92717
https://doi.org/10.1115/ICONE29-92717
View Paper titled, Simulation on the Process of Core Molten Pool Formation and Corium Relocation in the Core Region
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Topics: Accidents, Algorithms, Collapse, Dams, Flow (Dynamics), Fuel rods, Geometry, Heat transfer, Melting, Porous materials
Proceedings Papers

Evaluation on Weldability of Nickel-Base Alloy Weld Materials With High Chromium Content

Yoshinori Katayama, Takahiro Hayashi, Daiki Tanaka, Hidenori Takahashi
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A003, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89096
https://doi.org/10.1115/ICONE29-89096
View Paper titled, Evaluation on Weldability of Nickel-Base Alloy Weld Materials With High Chromium Content
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Topics: Alloys, Cracking (Materials), Ductility, Fracture (Process), Nickel, Solidification
Proceedings Papers

Study on the Substitute Nuclides of Actinides in High-Level Radioactive Waste Liquid

Yingzhe Du, Lili Li, Kunfeng Li, Peng Lin, Yugang Zhang, Juan Diwu
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A040, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93771
https://doi.org/10.1115/ICONE29-93771
View Paper titled, Study on the Substitute Nuclides of Actinides in High-Level Radioactive Waste Liquid
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Topics: Nuclides, Radioactive wastes, Glass, Solidification, Chemical properties, Electron configuration, Molecular orbitals, Nuclear reactions, Oxidation
Proceedings Papers

Preparation and Properties of Ceramic Solidified Product Containing Cs and Sr

Hongji Sang, Zhengcheng Gu, Zheng Cui, Ruoxue Zou, Yan Wu
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A031, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92765
https://doi.org/10.1115/ICONE29-92765
View Paper titled, Preparation and Properties of Ceramic Solidified Product Containing Cs and Sr
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Topics: Ceramics, Solidification, Sintering, Crystallization, Half-life, Heat, Melting, Minerals, Radioactivity, Work hardening
Proceedings Papers

High Efficient Mineralization of Cesium in Waste Liquid by Hydrothermal Method

Kai Gao, Wendong Feng, Xiaojun Yan, Xiaobin Guo, Xiaoyan Cui, Xiliang Guo
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-90716
https://doi.org/10.1115/ICONE29-90716
View Paper titled, High Efficient Mineralization of Cesium in Waste Liquid by Hydrothermal Method
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Topics: Aluminum, Cements (Adhesives), Exhaust systems, Glass, High temperature, Ion exchange, Nuclear fuel cycle, Phase transition temperature, Raw materials, Sewage
Proceedings Papers

Numerical Investigation of Safety System Parameters in Molten Salt Reactor: Wall Effect on Freeze Valve Opening Time

Muhammad Ilham, Indarta Kuncoro Aji, Tomio Okawa
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, V001T03A003, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64134
https://doi.org/10.1115/ICONE28-64134
View Paper titled, Numerical Investigation of Safety System Parameters in Molten Salt Reactor: Wall Effect on Freeze Valve Opening Time
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Topics: Melting, Molten salt reactors, Safety, Solidification, Valves
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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63770
https://doi.org/10.1115/ICONE28-63770
View Paper titled, Investigation on Solidification Behavior of Deposited Metal by GTAW With ERNiCrFe-13 Wire
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Topics: Gas tungsten arc welding, Metals, Solidification, Wire, Temperature, Cracking (Materials), Fracture (Process), Differential scanning calorimetry, Ductility, Lasers
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Validation of a Multi-Phase Model for Eutectic Reaction Between Stainless Steel and Boron Carbide

Xiaoxing Liu, Koji Morita, Hidemasa Yamano
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A019, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16175
https://doi.org/10.1115/ICONE2020-16175
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Validation of a Multi-Phase Model for Eutectic Reaction Between Stainless Steel and Boron Carbide
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Topics: Accidents, Boron, Melting, Sodium fast reactors, Stainless steel, Equilibrium (Physics), Fast neutron reactors, Heat, Mass transfer, Safety
Proceedings Papers

Numerical Study of Fuel Melting and Molten Migration Based on the MPS Method

Zhong Lei, Jian Deng, Wei Li, Xiaoli Wu, Chunrui Deng
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A045, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16806
https://doi.org/10.1115/ICONE2020-16806
View Paper titled, Numerical Study of Fuel Melting and Molten Migration Based on the MPS Method
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Topics: Accidents, Fuels, High temperature, Melting, Particulate matter, Solidification
Proceedings Papers

Development of Numerical Simulation Method to Evaluate Molten Material Behaviors in Nuclear Reactors: Estimation of Fuel Debris Distribution in the Pedestal

Susumu Yamashita, Hiroyuki Yoshida
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A033, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82088
https://doi.org/10.1115/ICONE26-82088
View Paper titled, Development of Numerical Simulation Method to Evaluate Molten Material Behaviors in Nuclear Reactors: Estimation of Fuel Debris Distribution in the Pedestal
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Topics: Computer simulation, Fuels, Nuclear reactors, Accidents, Melting, Alpha decay, Cladding systems (Building), Computational fluid dynamics, Fukushima nuclear disaster, Japan, 2011, Heat
Proceedings Papers

Fourier-Bessel Series Model for the Stefan Problem With Internal Heat Generation in Cylindrical Coordinates

Lyudmyla Barannyk, John Crepeau, Patrick Paulus, Ali Siahpush
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A002, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81009
https://doi.org/10.1115/ICONE26-81009
View Paper titled, Fourier-Bessel Series Model for the Stefan Problem With Internal Heat Generation in Cylindrical Coordinates
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Topics: Heat, Differential equations, Melting, Solidification, Steady state, Approximation, Fuel rods, Temperature gradient, Temperature profiles, Transients (Dynamics)
Proceedings Papers

SIRIO: An Experimental Facility for a New Heat Removal System Passively Controlled by Non-Condensable Gases

R. Marinari, M. Tarantino, F. S. Nitti, A. Alemberti, M. Caramello, A. Achilli, R. Ferri, E. Rizzo, F. Giannetti
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A054, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82379
https://doi.org/10.1115/ICONE26-82379
View Paper titled, SIRIO: An Experimental Facility for a New Heat Removal System Passively Controlled by Non-Condensable Gases
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Topics: Gases, Heat, Coolants, Safety, Design, Computer simulation, Freezing, Liquid metals, Solidification, Accidents
Proceedings Papers

Injectable Sacrificial Material System to Contain Ex-Vessel Molten Corium in Nuclear Accidents

David L. Y. Louie, Yifeng Wang, Rekha Rao, Alec Kucala, Jessica Kruichak
Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A038, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81440
https://doi.org/10.1115/ICONE26-81440
View Paper titled, Injectable Sacrificial Material System to Contain Ex-Vessel Molten Corium in Nuclear Accidents
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Topics: Accidents, Vessels, Light water reactors, Modeling, Water, Cavities, Conceptual design, Concretes, Containment, Cooling
Proceedings Papers

Tackling Coolant Freezing in Generation-IV Molten Salt Reactors

N. Le Brun, A. Charogiannis, G. F. Hewitt, C. N. Markides
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A067, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67984
https://doi.org/10.1115/ICONE25-67984
View Paper titled, Tackling Coolant Freezing in Generation-IV Molten Salt Reactors
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Topics: Coolants, Freezing, Molten salt reactors, Internal flow, Transients (Dynamics), Accidents, Computer simulation, Fluids, Fluorescence, Heat
Proceedings Papers

Proven Technologies for the Solidification of Complex Liquid Radioactive Waste (LRW): Global Case Studies of Applications and Disposal Options

Dennis Kelley
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A002, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66081
https://doi.org/10.1115/ICONE25-66081
View Paper titled, Proven Technologies for the Solidification of Complex Liquid Radioactive Waste (LRW): Global Case Studies of Applications and Disposal Options
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Topics: Radioactive wastes, Solidification, Nuclear power stations, Hazards, Isotopes, Nuclear decommissioning, Polymers, Storage, Warfare
Proceedings Papers

The Study on High Efficiency Solidification Technology of Radioactive Liquid Waste Containing Boron

Yaguang Wang, Jinsong Zhang, Yunming Chen, Bing Li, Qi Cao
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A031, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67665
https://doi.org/10.1115/ICONE25-67665
View Paper titled, The Study on High Efficiency Solidification Technology of Radioactive Liquid Waste Containing Boron
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Topics: Boron, Solidification, Cements (Adhesives), Compressive strength, Containment, Engineering standards, Radioactive waste disposal
Proceedings Papers

Melting Simulation Using a Particle Method With Angular Momentum Conservation

Masahiro Kondo, Shota Ueda, Koji Okamoto
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A033, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67588
https://doi.org/10.1115/ICONE25-67588
View Paper titled, Melting Simulation Using a Particle Method With Angular Momentum Conservation
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Topics: Angular momentum, Melting, Particulate matter, Simulation, Geometry, Accidents, Cantilevers, Dams, Nuclear power stations, Solidification
Proceedings Papers

Development of Numerical Simulation Method for Melt Relocation Behavior in Nuclear Reactors: Validation of Applicability for Actual Core Support Structures

Susumu Yamashita, Kazuyuki Tokushima, Masaki Kurata, Kazuyuki Takase, Hiroyuki Yoshida
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A026, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60453
https://doi.org/10.1115/ICONE24-60453
View Paper titled, Development of Numerical Simulation Method for Melt Relocation Behavior in Nuclear Reactors: Validation of Applicability for Actual Core Support Structures
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Topics: Computer simulation, Nuclear reactors, High temperature, Solidification, Computer-aided design, Flow (Dynamics), Fluids, Fukushima nuclear disaster, Japan, 2011, Heat transfer, Nuclear power stations