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Journal Articles

ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code

Tommaso Del Moro, Pierdomenico Lorusso, Fabio Giannetti, Mariano Tarantino, Marco Caramello, Daniele Mazzi, Marin Constantin

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041301.

Paper No: NERS-22-1165

DOI: https://doi.org/10.1115/1.4056973

Published Online: March 13, 2023

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Topics: Cycles, Heat exchangers, Sensitivity analysis, Water, Fast neutron reactors, Conceptual design, Temperature, Heat, Bathythermographs, Geometry

Journal Articles

Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres

Olugbenga O. Noah, Johan F. Slabber, Josua P. Meyer

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031403.

Paper No: NERS-22-1020

DOI: https://doi.org/10.1115/1.4056239

Published Online: February 8, 2023

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Topics: Fluids, Heat transfer, Particulate matter, Simulation, Temperature, Flow (Dynamics), Design, Fuels, Safety, Natural convection

Journal Articles

Experimental Investigation on Debris Bed Quenching With Additional Non-Condensable Gas Injection

Markus Petroff, Rudi Kulenovic, Jörg Starflinger

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041702.

Paper No: NERS-21-1028

DOI: https://doi.org/10.1115/1.4051876

Published Online: September 3, 2022

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Topics: Floods, Particulate matter, Quenching (Metalworking), Temperature, Test facilities, Water, Flow (Dynamics), Concretes

Journal Articles

Void Fraction Measurement and Prediction of Two-Phase Boiling Flows in a Tubular Test Section

Qingqing Liu, Julio Diaz, Victor Petrov, Adam Burak, Annalisa Manera, Joseph Kelly, Xiaodong Sun

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021403.

Paper No: NERS-21-1164

DOI: https://doi.org/10.1115/1.4055002

Published Online: September 2, 2022

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Topics: Boiling, Densitometers, Flow (Dynamics), Porosity, X-rays, Water, Flow visualization, Two-phase flow, Instrumentation, Wall temperature

Journal Articles

Assessment of Filtered Containment Venting Strategies for Mitigating Severe Accident Consequences at a Generic Single-Unit CANDU

M. D. Shah, A. C. Morreale, L. S. Lebel

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011701.

Paper No: NERS-22-1025

DOI: https://doi.org/10.1115/1.4055258

Published Online: September 2, 2022

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Topics: Accidents, Containment, Failure, Pressure, Water

Journal Articles

Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool

Antonio Guglielmelli, Stefano Ederli, Fulvio Mascari, Federico Rocchi, Pietro Maccari

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041602.

Paper No: NERS-21-1018

DOI: https://doi.org/10.1115/1.4054514

Published Online: June 24, 2022

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Topics: Accidents, Cooling, Emissions, Fukushima nuclear disaster, Japan, 2011, Meteorology, Nuclear power stations, Simulation, Spent nuclear fuels, Wind, Wind velocity

Journal Articles

Possible Implementation of Ex-Core Measurement in TEPLATOR Graphite Reflector

Eva Vilímová, Tomáš Peltan, Jana Jiřičková

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041505.

Paper No: NERS-21-1013

DOI: https://doi.org/10.1115/1.4050990

Published Online: June 15, 2022

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Topics: Graphite, Neutron flux, Neutrons, Sensors, Spent nuclear fuels, Water, Fuels

Journal Articles

Water Hammers Exploded the Nuclear Power Plants at Fukushima Daiichi

Robert A. Leishear

ASME J of Nuclear Rad Sci. January 2023, 9(1): 014702.

Paper No: NERS-21-1058

DOI: https://doi.org/10.1115/1.4054004

Published Online: June 10, 2022

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Topics: Explosions, Hydrogen, Water

Journal Articles

Radon and Exhalation Rate Measurement of Soil Samples in Al-Amiriya Area in Baghdad Governorate Using a Nuclear Track Detector

Basim Khalaf Rejah

ASME J of Nuclear Rad Sci. January 2023, 9(1): 014501.

Paper No: NERS-22-1001

DOI: https://doi.org/10.1115/1.4054619

Published Online: June 7, 2022

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Topics: Sensors, Soil, Uranium, Nuclear track detectors, Bridges (Structures), Rocks, Radiation (Physics), Water

Journal Articles

Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER

Benjamin Blaisot, Emmanuel Porcheron, Olivier Praud, Véronique Roig

ASME J of Nuclear Rad Sci. July 2022, 8(3): 032301.

Paper No: NERS-21-1149

DOI: https://doi.org/10.1115/1.4053828

Published Online: June 1, 2022

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Topics: Boiling, Coolants, Drops, Dust, Ejectors, Flow (Dynamics), Pressure, Sprays, Vacuum, Water

Journal Articles

Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels

Ayman M. Bayomy, Blair P. Bromley, Armando Nava Dominguez, Samuel Kelly

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031601.

Paper No: NERS-21-1184

DOI: https://doi.org/10.1115/1.4053829

Published Online: June 1, 2022

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Topics: Fuels, Manufacturing, Temperature, Water

Journal Articles

Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels

D. G. Watts, F. P. Adams, E. Masala, L. Blomeley, B. P. Bromley

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031501.

Paper No: NERS-21-1118

DOI: https://doi.org/10.1115/1.4054079

Published Online: May 26, 2022

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Topics: Fuels, Modeling, Physics, Pressurized water reactors, Water, Neutrons, High temperature

Journal Articles

Assessment of Spray and Pool Scrubbing Efficiencies for Means of Mitigation Against Aerosol Dispersion in the Context of Fuel Debris Retrieval at Fukushima Daiichi: Part II

Emmanuel Porcheron, Yohan Leblois, Thomas Gelain, Christophe Chagnot, Christophe Journeau, Damien Roulet

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031702.

Paper No: NERS-21-1064

DOI: https://doi.org/10.1115/1.4051538

Published Online: May 26, 2022

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Topics: Aerosols, Particulate matter, Sprays, Laser cutting, Drops, Fuels, Water, Computer simulation, Fukushima nuclear disaster, Japan, 2011

Journal Articles

Assessment of Spray and Pool Scrubbing Efficiencies for Means of Mitigation Against Aerosol Dispersion in the Context of Fuel Debris Retrieval at Fukushima Daiichi: Part I

Emmanuel Porcheron, Yohan Leblois, Thomas Gelain, Christophe Chagnot, Christophe Journeau, Damien Roulet

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031701.

Paper No: NERS-20-1177

DOI: https://doi.org/10.1115/1.4051611

Published Online: May 26, 2022

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Topics: Aerosols, Sprays, Particulate matter, Laser cutting, Fuels, Water, Drops

Journal Articles

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

S. P. Saraswat, D. Ray, G. Mishra, D. Yadav, V. S. Bhadouria, P. Munshi, C. Allison

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403.

Paper No: NERS-21-1073

DOI: https://doi.org/10.1115/1.4052014

Published Online: May 26, 2022

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Topics: Accidents, Boiling water reactors, Containment, Design, Pressure, Safety, Steam, Water, Heat, Economics

Journal Articles

Experimental Investigation of Melt Coolability Behavior in an Ex-Vessel Core Catcher: The Effect of Flooding Time

Ganesh V, Parimal P. Kulkarni, Arun K. Nayak

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031401.

Paper No: NERS-21-1060

DOI: https://doi.org/10.1115/1.4053220

Published Online: May 26, 2022

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Topics: Floods, Temperature, Vessels, Water

Journal Articles

Thermal Stratification in a Pool With Submerged Heater Under Low Frequency Excitation

S. P. Chauhan, D. K. Chandraker, Naveen Kumar

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031405.

Paper No: NERS-21-1106

DOI: https://doi.org/10.1115/1.4053221

Published Online: May 26, 2022

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Topics: Excitation, Thermal stratification, Water, Temperature gradient, Temperature, Heat

Journal Articles

Mechanical and Microstructural Characterization of Inconel 625 Welds After Corrosion at Supercritical Water Conditions

German Cota-Sanchez, Lin Xiao, Stephane Rousseau

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031107.

Paper No: NERS-22-1007

DOI: https://doi.org/10.1115/1.4054637

Published Online: May 25, 2022

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Topics: Corrosion, Welding, Phase diagrams, Water, Welded joints, Testing

Journal Articles

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

A. M. Baisov, A. N. Churkin, V. I. Deev, V. S. Kharitonov

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031101.

Paper No: NERS-21-1101

DOI: https://doi.org/10.1115/1.4053049

Published Online: March 22, 2022

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Topics: Coolants, Fluids, Fuel rods, Heat transfer, Momentum, Temperature, Water, Wall temperature, Flow (Dynamics), Testing

Journal Articles

Deposition of ITER Vacuum Vessel Dust Inside the Pressure Suppression System During a Loss of Coolant Accident: Experimental and Numerical Analyses

Miriam Ibba, Alessio Pesetti, Michele Raucci, Flavio Parozzi, Roberta Lazzeri, Donato Aquaro

ASME J of Nuclear Rad Sci. October 2022, 8(4): 042301.

Paper No: NERS-21-1025

DOI: https://doi.org/10.1115/1.4050768

Published Online: March 16, 2022

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Topics: Dust, Water, Containers, Vessels, Pipes

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Journal citation

NARROW

ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code

Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres

Experimental Investigation on Debris Bed Quenching With Additional Non-Condensable Gas Injection

Void Fraction Measurement and Prediction of Two-Phase Boiling Flows in a Tubular Test Section

Assessment of Filtered Containment Venting Strategies for Mitigating Severe Accident Consequences at a Generic Single-Unit CANDU

Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool

Possible Implementation of Ex-Core Measurement in TEPLATOR Graphite Reflector

Water Hammers Exploded the Nuclear Power Plants at Fukushima Daiichi

Radon and Exhalation Rate Measurement of Soil Samples in Al-Amiriya Area in Baghdad Governorate Using a Nuclear Track Detector

Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER

Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels

Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels

Assessment of Spray and Pool Scrubbing Efficiencies for Means of Mitigation Against Aerosol Dispersion in the Context of Fuel Debris Retrieval at Fukushima Daiichi: Part II

Assessment of Spray and Pool Scrubbing Efficiencies for Means of Mitigation Against Aerosol Dispersion in the Context of Fuel Debris Retrieval at Fukushima Daiichi: Part I

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

Experimental Investigation of Melt Coolability Behavior in an Ex-Vessel Core Catcher: The Effect of Flooding Time

Thermal Stratification in a Pool With Submerged Heater Under Low Frequency Excitation

Mechanical and Microstructural Characterization of Inconel 625 Welds After Corrosion at Supercritical Water Conditions

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

Deposition of ITER Vacuum Vessel Dust Inside the Pressure Suppression System During a Loss of Coolant Accident: Experimental and Numerical Analyses

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