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Journal Articles

Post-Test Analyses of the CMMR-4 Test

Takuya Yamashita, Hiroshi Madokoro, Ikken Sato

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021701.

Paper No: NERS-21-1055

DOI: https://doi.org/10.1115/1.4051443

Published Online: October 19, 2021

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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

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011308.

Paper No: NERS-21-1042

DOI: https://doi.org/10.1115/1.4051448

Published Online: August 3, 2021

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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

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021602.

Paper No: NERS-20-1147

DOI: https://doi.org/10.1115/1.4048899

Published Online: November 16, 2020

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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

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021801.

Paper No: NERS-20-1140

DOI: https://doi.org/10.1115/1.4048632

Published Online: October 30, 2020

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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

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011703.

Paper No: NERS-19-1184

DOI: https://doi.org/10.1115/1.4048008

Published Online: October 5, 2020

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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

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011603.

Paper No: NERS-19-1177

DOI: https://doi.org/10.1115/1.4047919

Published Online: October 2, 2020

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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

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021105.

Paper No: NERS-19-1051

DOI: https://doi.org/10.1115/1.4045180

Published Online: January 29, 2020

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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

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021113.

Paper No: NERS-19-1047

DOI: https://doi.org/10.1115/1.4045450

Published Online: January 29, 2020

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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

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011108.

Paper No: NERS-19-1046

DOI: https://doi.org/10.1115/1.4044751

Published Online: November 8, 2019

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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

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041206.

Paper No: NERS-18-1115

DOI: https://doi.org/10.1115/1.4043106

Published Online: July 19, 2019

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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

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030911.

Paper No: NERS-18-1121

DOI: https://doi.org/10.1115/1.4043199

Published Online: April 16, 2019

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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

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011001.

Paper No: NERS-17-1166

DOI: https://doi.org/10.1115/1.4040649

Published Online: January 24, 2019

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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

ASME J of Nuclear Rad Sci. October 2016, 2(4): 041005.

Paper No: NERS-15-1151

DOI: https://doi.org/10.1115/1.4033397

Published Online: October 12, 2016

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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

ASME J of Nuclear Rad Sci. April 2016, 2(2): 021002.

Paper No: NERS-15-1009

DOI: https://doi.org/10.1115/1.4031842

Published Online: February 29, 2016

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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

ASME J of Nuclear Rad Sci. July 2015, 1(3): 031003.

Paper No: NERS-14-1026

DOI: https://doi.org/10.1115/1.4029790

Published Online: May 20, 2015

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Topics: Alloys, Liquid metals, Melting, Metals, Neodymium, Separation (Technology), Thermodynamics

Journal citation

NARROW

Post-Test Analyses of the CMMR-4 Test

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

Heat Transfer in Induction Melting of Aluminum Oxide in Cold Crucible

Manipulation System for Measuring Heat Flux in Radioactive Melt

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

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

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

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

Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels

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

Preliminary Experiments While Designing a Cold Crucible for Metal Melting

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

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

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

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

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