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Journal Articles

Advancement Toward the Experimental Measurement of the Lead–Bismuth Eutectic Thermal Properties Using Differential Scanning Calorimetry Technique

Satya Prakash Saraswat, Nicola Forgione, Massimo Emilio Angiolini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021302.
Paper No: NERS-23-1045
https://doi.org/10.1115/1.4063572
Published Online: October 20, 2023
View Article titled, Advancement Toward the Experimental Measurement of the Lead–Bismuth Eutectic Thermal Properties Using Differential Scanning Calorimetry Technique
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Topics: Calibration, Differential scanning calorimetry, Heating, Latent heat, Melting, Melting point, Specific heat, Temperature, Thermal properties, Uncertainty
Journal Articles

A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors

Muhammad Ilham, Tomio Okawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041107.
Paper No: NERS-22-1162
https://doi.org/10.1115/1.4062879
Published Online: July 17, 2023
View Article titled, A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors
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Topics: Molten salt reactors, Simulation, Wall thickness, Safety, Computer simulation, Design, Temperature, Heat conduction, Melting, Solidification
Journal Articles

Post-Test Analyses of the CMMR-4 Test

Takuya Yamashita, Hiroshi Madokoro, Ikken Sato
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021701.
Paper No: NERS-21-1055
https://doi.org/10.1115/1.4051443
Published Online: October 19, 2021
View Article titled, Post-Test Analyses of the CMMR-4 Test
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Topics: Blades, Boiling water reactors, Cutting, Fuels, Heating, Melting, Water, Temperature, Accidents, Permeability
Journal Articles

Ablation of a Solid Material by High-Temperature Liquid Jet Impingement: An Application to Corium Jet Impingement on a Sodium Fast Reactor Core-Catcher

Alexandre Lecoanet, Michel Gradeck, Xiaoyang Gaus-Liu, Thomas Cron, Beatrix Fluhrer, Frédéric Payot, Christophe Journeau, Nicolas Rimbert
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2022, 8(1): 011308.
Paper No: NERS-21-1042
https://doi.org/10.1115/1.4051448
Published Online: August 3, 2021
View Article titled, Ablation of a Solid Material by High-Temperature Liquid Jet Impingement: An Application to Corium Jet Impingement on a Sodium Fast Reactor Core-Catcher
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Topics: Ablation (Vaporization technology), Heat transfer, Melting, Sodium fast reactors, Cavities, High temperature, Ice, Design, Temperature, Water
Journal Articles

Heat Transfer in Induction Melting of Aluminum Oxide in Cold Crucible

David Rot, Jan Hrbek, Jakub Jirinec
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021602.
Paper No: NERS-20-1147
https://doi.org/10.1115/1.4048899
Published Online: November 16, 2020
View Article titled, Heat Transfer in Induction Melting of Aluminum Oxide in Cold Crucible
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Topics: Aluminum, Cooling, Design, Electromagnetic induction, Heat transfer, Melting, Temperature, Water, Inductors, Heat flux
Journal Articles

Manipulation System for Measuring Heat Flux in Radioactive Melt

Michal Knedlík, David Rot, Jan Hrbek
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2021, 7(2): 021801.
Paper No: NERS-20-1140
https://doi.org/10.1115/1.4048632
Published Online: October 30, 2020
View Article titled, Manipulation System for Measuring Heat Flux in Radioactive Melt
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Topics: Control algorithms, Electromagnetic induction, Heat flux, Manipulators, Melting, Safety, Temperature, Testing, User interfaces, Computer software
Journal Articles

Finite Element Model of a Melting Terminal Debris Bed in a CANDU Calandria

R. David
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011703.
Paper No: NERS-19-1184
https://doi.org/10.1115/1.4048008
Published Online: October 5, 2020
View Article titled, Finite Element Model of a Melting Terminal Debris Bed in a CANDU Calandria
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Topics: Accidents, Finite element model, Heat, Melting, Porosity, Temperature, Transients (Dynamics), Uranium, Materials properties
Journal Articles

Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors

S. Majumdar, J. Kishor, A. N. Behera, B. Vishwanadh, A. Borgohain, R. Kapoor, R. Tewari, V. Kain, Madangopal Krishnan, G. K. Dey, S. Banerjee
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011603.
Paper No: NERS-19-1177
https://doi.org/10.1115/1.4047919
Published Online: October 2, 2020
View Article titled, Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors
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Topics: Alloys, Creep, Errors, Cathode ray oscilloscopes, Electron beams, High temperature, Corrosion, Melting
Journal Articles

An Experimental and Numerical Study of Wall Effect on Freeze Valve Performance in a Molten Salt Reactor

Indarta Kuncoro Aji, Tokushima Tatsuya, Motoyasu Kinoshita, Tomio Okawa
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021105.
Paper No: NERS-19-1051
https://doi.org/10.1115/1.4045180
Published Online: January 29, 2020
View Article titled, An Experimental and Numerical Study of Wall Effect on Freeze Valve Performance in a Molten Salt Reactor
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Topics: Cylinders, Molten salt reactors, Temperature, Valves, Brass (Metal), Thermal conductivity, Melting, Computer simulation, Copper, Fuels
Journal Articles

Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident

Yuta Abe, Takuya Yamashita, Ikken Sato, Toshio Nakagiri, Akihiro Ishimi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2020, 6(2): 021113.
Paper No: NERS-19-1047
https://doi.org/10.1115/1.4045450
Published Online: January 29, 2020
View Article titled, Development of Experimental Technology for Simulated Fuel-Assembly Heating to Address Core-Material-Relocation Behavior During Severe Accident
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Topics: Fuels, Heating, Manufacturing, Plasmas (Ionized gases), Accidents, Temperature, Permeability, Melting, Blades
Journal Articles

Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels

B. Szpunar, J. A. Szpunar
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011108.
Paper No: NERS-19-1046
https://doi.org/10.1115/1.4044751
Published Online: November 8, 2019
View Article titled, Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels
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Topics: Accidents, Atoms, Diffusion (Physics), Fuel rods, Fuels, Helium, Nuclear fuels, Oxygen, Temperature, Temperature gradient
Journal Articles

Experimental Investigation of Melt Coolability and Ablation Behavior of Oxidic Sacrificial Material at Prototypic Conditions in Scaled Down Core Catcher

Samyak S. Munot, Ganesh V, Parimal P. Kulkarni, Arun K. Nayak
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041206.
Paper No: NERS-18-1115
https://doi.org/10.1115/1.4043106
Published Online: July 19, 2019
View Article titled, Experimental Investigation of Melt Coolability and Ablation Behavior of Oxidic Sacrificial Material at Prototypic Conditions in Scaled Down Core Catcher
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Topics: Ablation (Vaporization technology), Bricks, Cavities, Temperature, Thermocouples, Vessels, Water, Heat, Accidents, Floods
Journal Articles

Preliminary Experiments While Designing a Cold Crucible for Metal Melting

David Rot, Jakub Jiřinec
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2019, 5(3): 030911.
Paper No: NERS-18-1121
https://doi.org/10.1115/1.4043199
Published Online: April 16, 2019
View Article titled, Preliminary Experiments While Designing a Cold Crucible for Metal Melting
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Topics: Alloys, Computer simulation, Design, Electromagnetic induction, Inductors, Melting, Metals, Stress, Magnetohydrodynamics, Generators
Journal Articles

Development and Validation of SAS4A Code and Its Application to Analyses on Severe Flow Blockage Accidents in a Sodium-Cooled Fast Reactor

Yoshitaka Fukano
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011001.
Paper No: NERS-17-1166
https://doi.org/10.1115/1.4040649
Published Online: January 24, 2019
View Article titled, Development and Validation of SAS4A Code and Its Application to Analyses on Severe Flow Blockage Accidents in a Sodium-Cooled Fast Reactor
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Topics: Cladding systems (Building), Control systems, Coolants, Flow (Dynamics), Fuels, Sodium fast reactors, Accidents, Safety, Melting, Signals
Journal Articles

Phenomenological Analysis of Melt Progression in LWRS: Proposal of an In-Vessel Corium Progression Scenario in the Unit 1 of Fukushima Dai-ichi Nuclear Power Plant

Payot Frédéric, Seiler Jean-Marie
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2016, 2(4): 041005.
Paper No: NERS-15-1151
https://doi.org/10.1115/1.4033397
Published Online: October 12, 2016
View Article titled, Phenomenological Analysis of Melt Progression in LWRS: Proposal of an In-Vessel Corium Progression Scenario in the Unit 1 of Fukushima Dai-ichi Nuclear Power Plant
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Topics: Failure, Fukushima nuclear disaster, Japan, 2011, Heat flux, Jet pumps, Nuclear power stations, Seas, Vessels, Water, Light water reactors, Melting
Journal Articles

The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA

Jun Wang, Yuqiao Fan, Yapei Zhang, Xinghe Ni, Wenxi Tian, Michael L. Corradini, Guanghui Su, Suizheng Qiu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021002.
Paper No: NERS-15-1009
https://doi.org/10.1115/1.4031842
Published Online: February 29, 2016
View Article titled, The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCA
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Topics: Accidents, Flow (Dynamics), Temperature, Vessels, Melting, Hydrogen
Journal Articles

Thermodynamics of Nuclear Waste Reprocessing: Separation of Lanthanides Using Liquid Metals and Alloys

Stanislav Yu. Melchakov, Leonid F. Yamshchikov, Vladimir A. Volkovich, Alexander G. Osipenko
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031003.
Paper No: NERS-14-1026
https://doi.org/10.1115/1.4029790
Published Online: May 20, 2015
View Article titled, Thermodynamics of Nuclear Waste Reprocessing: Separation of Lanthanides Using Liquid Metals and Alloys
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Topics: Alloys, Liquid metals, Melting, Metals, Neodymium, Separation (Technology), Thermodynamics