1-20 of 116
Melting
Close
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Experimental Study of the Heat Transfer Performance and the Crust of the Two-Layer Stratified Melting Corium

Available to Purchase

Mengyi Wang, Fengyang Quan, Jie Pei, Wei Li, Yidan Yuan
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T11A006, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135101
https://doi.org/10.1115/ICONE31-135101
View Paper titled, Experimental Study of the Heat Transfer Performance and the Crust of the Two-Layer Stratified Melting Corium
Open the PDF for Experimental Study of the Heat Transfer Performance and the Crust of the Two-Layer Stratified Melting Corium in another window
Topics: Density, Heat flux, Heat transfer, Melting
Proceedings Papers

Estimation of the 1F2 Core Thermal Status During the Core Heat-Up Phase With MELCOR-2.2

Available to Purchase

Shotaro Osako, Xin Li, Akifumi Yamaji
Proc. ASME. ICONE29, Volume 7A: Thermal-Hydraulics and Safety Analysis, V07AT07A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-89102
https://doi.org/10.1115/ICONE29-89102
View Paper titled, Estimation of the 1F2 Core Thermal Status During the Core Heat-Up Phase With MELCOR-2.2
Open the PDF for Estimation of the 1F2 Core Thermal Status During the Core Heat-Up Phase With MELCOR-2.2 in another window
Topics: Accidents, Fuels, Fukushima nuclear disaster, Japan, 2011, Heat, Oxidation, Melting, Temperature, Leakage, Nuclear decommissioning, Nuclear power stations
Proceedings Papers

Development of an MPS Code for Corium Behavior Analysis

Available to Purchase

Lijun Jian, Hongfan Lu, Peng Yu, Yidan Yuan
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A013, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91422
https://doi.org/10.1115/ICONE29-91422
View Paper titled, Development of an MPS Code for Corium Behavior Analysis
Open the PDF for Development of an MPS Code for Corium Behavior Analysis in another window
Topics: Accidents, Alloys, Collapse, Deformation, Drops, Enthalpy, Fukushima nuclear disaster, Japan, 2011, Heat transfer, Melting, Oscillations
Proceedings Papers

Preparation and Properties of Ceramic Solidified Product Containing Cs and Sr

Available to Purchase

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
Open the PDF for Preparation and Properties of Ceramic Solidified Product Containing Cs and Sr in another window
Topics: Ceramics, Solidification, Sintering, Crystallization, Half-life, Heat, Melting, Minerals, Radioactivity, Work hardening
Proceedings Papers

Study on the Growth and Scintillation Properties of CLLB Crystals

Available to Purchase

Kun Wu, Leilei Zhang, Haijun Li, Guangwei Huang, Jiaming Li, Libin Wang, Siyuan Zhang, Zhiyuan Li, Qinhua Wei, Chunzhi Zhou, Zungang Wang, Huilan Liu, Hongying Zhu, Yushou Song
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A011, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91215
https://doi.org/10.1115/ICONE29-91215
View Paper titled, Study on the Growth and Scintillation Properties of CLLB Crystals
Open the PDF for Study on the Growth and Scintillation Properties of CLLB Crystals in another window
Topics: Crystals, Melting, Neutrons, Resolution (Optics), Gamma rays, Signals, Crystal growth, Density, Furnaces, Photons
Proceedings Papers

Study on the High Temperature Melting Treatment of Nuclear Waste Glass Fiber

Available to Purchase

ChunYu Liu, YanLi Wen
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A041, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93802
https://doi.org/10.1115/ICONE29-93802
View Paper titled, Study on the High Temperature Melting Treatment of Nuclear Waste Glass Fiber
Open the PDF for Study on the High Temperature Melting Treatment of Nuclear Waste Glass Fiber in another window
Topics: Filters, Glass fibers, High temperature, Melting, Radioactive wastes
Proceedings Papers

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

Available to Purchase

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
Open the PDF for Simulation on the Process of Core Molten Pool Formation and Corium Relocation in the Core Region in another window
Topics: Accidents, Algorithms, Collapse, Dams, Flow (Dynamics), Fuel rods, Geometry, Heat transfer, Melting, Porous materials
Proceedings Papers

Non-Destructive Examination of PWR Steam Generator Tube-Tube Plate Welds After Repairing Melting Damage

Available to Purchase

Yan Zhang, JianLei Zhang, Zhonghe Cheng
Proc. ASME. ICONE29, Volume 10: Advanced Methods of Manufacturing for Nuclear Reactors and Components, V010T10A045, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92978
https://doi.org/10.1115/ICONE29-92978
View Paper titled, Non-Destructive Examination of PWR Steam Generator Tube-Tube Plate Welds After Repairing Melting Damage
Open the PDF for Non-Destructive Examination of PWR Steam Generator Tube-Tube Plate Welds After Repairing Melting Damage in another window
Topics: Boilers, Damage, Maintenance, Melting, Nondestructive evaluation, Pressurized water reactors, Welded joints
Proceedings Papers

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

Available to Purchase

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
Open the PDF for Numerical Investigation of Safety System Parameters in Molten Salt Reactor: Wall Effect on Freeze Valve Opening Time in another window
Topics: Melting, Molten salt reactors, Safety, Solidification, Valves
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (2) Kinetic Study on Eutectic Reaction Process Between Stainless Steel With Low Boron Carbide Concentration and Stainless Steel

Available to Purchase

Shin Kikuchi, Toshihide Takai, Hidemasa Yamano, Kan Sakamoto
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, V003T12A003, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-62252
https://doi.org/10.1115/ICONE28-62252
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (2) Kinetic Study on Eutectic Reaction Process Between Stainless Steel With Low Boron Carbide Concentration and Stainless Steel
Open the PDF for Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (2) Kinetic Study on Eutectic Reaction Process Between Stainless Steel With Low Boron Carbide Concentration and Stainless Steel in another window
Topics: Accidents, Boron, Melting, Sodium fast reactors, Stainless steel
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview and Progress Until 2019

Available to Purchase

Hidemasa Yamano, Toshihide Takai, Tomohiro Furukawa, Shin Kikuchi, Yuki Emura, Kenji Kamiyama, Hiroyuki Fukuyama, Hideo Higashi, Tsuyoshi Nishi, Hiromichi Ohta, Koji Morita, Kinya Nakamura
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, V003T12A008, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-63301
https://doi.org/10.1115/ICONE28-63301
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview and Progress Until 2019
Open the PDF for Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: (1) Project Overview and Progress Until 2019 in another window
Topics: Accidents, Melting, Sodium fast reactors, Stainless steel
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

Available to Purchase

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
Open the PDF for 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 in another window
Topics: Accidents, Boron, Melting, Sodium fast reactors, Stainless steel, Equilibrium (Physics), Fast neutron reactors, Heat, Mass transfer, Safety
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

Available to Purchase

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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16075
https://doi.org/10.1115/ICONE2020-16075
View Paper titled, 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
Open the PDF for 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 in another window
Topics: Accidents, Boron, Melting, Sodium fast reactors, Steel, Thermal analysis
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Thermophysical Properties of Eutectic Mixture Containing of High Concentration Boron in a Solid State

Available to Purchase

Toshihide Takai, Tomohiro Furukawa, 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, V002T08A006, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16091
https://doi.org/10.1115/ICONE2020-16091
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Thermophysical Properties of Eutectic Mixture Containing of High Concentration Boron in a Solid State
Open the PDF for Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Thermophysical Properties of Eutectic Mixture Containing of High Concentration Boron in a Solid State in another window
Topics: Accidents, Boron, Melting, Sodium fast reactors, Stainless steel
Proceedings Papers

Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Project Overview and Progress Until 2018

Available to Purchase

Hidemasa Yamano, Toshihide Takai, Tomohiro Furukawa, Shin Kikuchi, Yuki Emura, Kenji Kamiyama, Hiroyuki Fukuyama, Hideo Higashi, Tsuyoshi Nishi, Hiromichi Ohta, Xiaoxing Liu, Koji Morita, 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, V002T08A007, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16102
https://doi.org/10.1115/ICONE2020-16102
View Paper titled, Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Project Overview and Progress Until 2018
Open the PDF for Study on Eutectic Melting Behavior of Control Rod Materials in Core Disruptive Accidents of Sodium-Cooled Fast Reactors: Project Overview and Progress Until 2018 in another window
Topics: Accidents, Melting, Sodium fast reactors, Stainless steel
Proceedings Papers

Development of Three-Dimensional Distribution Visualization Technology for Boron Using Energy Resolved Neutron-Imaging System (RADEN)

Available to Purchase

Yuta Abe, Yusuke Tsuchikawa, Tetsuya Kai, Yoshihiro Matsumoto, Joseph D. Parker, Takenao Shinohara, Yuji Ohishi, Takashi Kamiyama, Yuji Nagae, Ikken Sato
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A050, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16723
https://doi.org/10.1115/ICONE2020-16723
View Paper titled, Development of Three-Dimensional Distribution Visualization Technology for Boron Using Energy Resolved Neutron-Imaging System (RADEN)
Open the PDF for Development of Three-Dimensional Distribution Visualization Technology for Boron Using Energy Resolved Neutron-Imaging System (RADEN) in another window
Topics: Boron, Fukushima nuclear disaster, Japan, 2011, Imaging, Melting, Neutrons, Nuclear decommissioning, Nuclear power stations, Visualization
Proceedings Papers

A Comparative Study of Constrained and Unconstrained Melting Inside a Sphere

Available to Purchase

Rohit Kothari, Shripad T. Revankar, Santosh K. Sahu, Shailesh I. Kundalwal
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A002, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16056
https://doi.org/10.1115/ICONE2020-16056
View Paper titled, A Comparative Study of Constrained and Unconstrained Melting Inside a Sphere
Open the PDF for A Comparative Study of Constrained and Unconstrained Melting Inside a Sphere in another window
Topics: Melting, Boundary-value problems, Composite materials, Computational fluid dynamics, Phase change materials, Temperature
Proceedings Papers

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

Available to Purchase

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
Open the PDF for Numerical Study of Fuel Melting and Molten Migration Based on the MPS Method in another window
Topics: Accidents, Fuels, High temperature, Melting, Particulate matter, Solidification
Proceedings Papers

Study on Cooling Process in a Reactor Vessel of Sodium-Cooled Fast Reactor Under Severe Accident: Velocity Measurement Experiments Simulating Operation of Decay Heat Removal Systems

Available to Purchase

Mitsuyo Tsuji, Kosuke Aizawa, Jun Kobayashi, Akikazu Kurihara, Yasuhiro Miyake
Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A046, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16796
https://doi.org/10.1115/ICONE2020-16796
View Paper titled, Study on Cooling Process in a Reactor Vessel of Sodium-Cooled Fast Reactor Under Severe Accident: Velocity Measurement Experiments Simulating Operation of Decay Heat Removal Systems
Open the PDF for Study on Cooling Process in a Reactor Vessel of Sodium-Cooled Fast Reactor Under Severe Accident: Velocity Measurement Experiments Simulating Operation of Decay Heat Removal Systems in another window
Topics: Accidents, Cooling, Flow (Dynamics), Heat, Reactor vessels, Sodium fast reactors, Velocity measurement, Fuels, Design, Heat exchangers
Proceedings Papers

The Effect of Initial Condition of Melt Jet on the Jet Breakup Phenomenon in the Subcooled Water Pool

Available to Purchase

Woo Hyun Jung, Hyun Sun Park, Kiyofumi Moriyama, Moo Hwan Kim
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A015, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82310
https://doi.org/10.1115/ICONE26-82310
View Paper titled, The Effect of Initial Condition of Melt Jet on the Jet Breakup Phenomenon in the Subcooled Water Pool
Open the PDF for The Effect of Initial Condition of Melt Jet on the Jet Breakup Phenomenon in the Subcooled Water Pool in another window
Topics: Subcooling, Water, Shapes, Uncertainty, Accidents, Cavities, Melting, Separation (Technology), Sluice gates, Temperature