Search Results | ASME J. of Nuclear Rad Sci.

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Journal Articles

Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors

Kazuo Yoshimura, Norihiro Doda, Kennichi Igawa, Masaaki Tanaka, Hidemasa Yamano

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021601.

Paper No: NERS-21-1160

DOI: https://doi.org/10.1115/1.4055328

Published Online: December 14, 2022

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Topics: Feedback, Sodium fast reactors, Temperature, Fuels, Sensitivity analysis, Density, Heat, Heat sinks, Dynamics (Mechanics), Coolants

Journal Articles

Long-Term Performance of Semi-Metallic Gaskets

Abdel-Hakim Bouzid, Shubhra Kanti Das

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1036

DOI: https://doi.org/10.1115/1.4056260

Published Online: November 15, 2022

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Topics: Gaskets, Graphite, Leakage, Temperature, High temperature, Relaxation (Physics), Weight (Mass), Creep, Metals, Oxidation

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.

Paper No: NERS-22-1020

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

Published Online: November 14, 2022

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Topics: Computer simulation, Heat transfer, Natural convection, Safety, Water, Particulate matter, Cladding systems (Building), Fuels, Nuclear fuels, Light water reactors

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

Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating

Rofida Hamad Khlifa, Nicolay N. Nikitenkov

ASME J of Nuclear Rad Sci. January 2023, 9(1): 012003.

Paper No: NERS-22-1044

DOI: https://doi.org/10.1115/1.4055012

Published Online: September 1, 2022

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Topics: Boron, Coatings, Fuels, Temperature, Cladding systems (Building), Neutrons, Accidents

Journal Articles

The Heat Capacity of PuO 2 at High Temperature: Molecular Dynamics Calculations

Rolando Calabrese

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041603.

Paper No: NERS-21-1027

DOI: https://doi.org/10.1115/1.4054941

Published Online: September 1, 2022

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Topics: Heat capacity, High temperature, Oxygen, Temperature, Molecular dynamics, Enthalpy, Modeling

Journal Articles

Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate

Michio Murase, Tomonori Suzuki, Yoichi Utanohara, Toshiya Takaki

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011401.

Paper No: NERS-22-1006

DOI: https://doi.org/10.1115/1.4054842

Published Online: July 19, 2022

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Topics: Flow (Dynamics), Steam, Temperature, Turbulence, Condensation, Flat plates, Boundary layer turbulence, Computational fluid dynamics, Computation

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

Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention

Ryotaro Sasaki, Akifumi Yamaji, Kyota Uchimura

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021501.

Paper No: NERS-21-1135

DOI: https://doi.org/10.1115/1.4053827

Published Online: June 15, 2022

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Topics: Design, Vessels, Cycles, Fuels, Temperature, Fast neutron reactors, Small modular reactors

Journal Articles

The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)

Witiwat Jiragoontansiri, Teerapat Woravisuttsarakul, Rinrada Sae-Pueng, Yanin Sukjai

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021401.

Paper No: NERS-21-1156

DOI: https://doi.org/10.1115/1.4054546

Published Online: June 15, 2022

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Topics: Airfoils, Flow (Dynamics), Geometry, Stress, Heat exchangers, Heat transfer, Temperature, Fluids, Structural analysis

Journal Articles

Transient Analysis of Passive Autocatalytic Hydrogen Recombiners Using Computational Fluid Dynamics

Ahsan Khan, Rab Nawaz, Ajmal Shah, Kamran Rasheed Qureshi

ASME J of Nuclear Rad Sci. January 2023, 9(1): 012001.

Paper No: NERS-21-1153

DOI: https://doi.org/10.1115/1.4054117

Published Online: June 7, 2022

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Topics: Computational fluid dynamics, Hydrogen, Temperature, Plates (structures)

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

Thermophysical Characteristics of Liquid Metal In-Bi-Sn Eutectic (Field's Metal) as a Similarity Coolant

Adam Lipchitz, Glenn Harvel, T. Sunagawa

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031301.

Paper No: NERS-21-1079

DOI: https://doi.org/10.1115/1.4053632

Published Online: May 26, 2022

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Topics: Density, Liquid metals, Metals, Temperature, Thermal conductivity, Viscosity, Specific heat, Alloys

Journal Articles

Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance

S. A. Cancemi, R. Lo Frano

ASME J of Nuclear Rad Sci. July 2022, 8(3): 034501.

Paper No: NERS-20-1206

DOI: https://doi.org/10.1115/1.4053689

Published Online: May 26, 2022

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Topics: Filters, Pipes, Signals, Stress, Temperature, Monitoring systems, Nuclear power stations

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

Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities

Yue Zou, Brian Derreberry

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031801.

Paper No: NERS-21-1040

DOI: https://doi.org/10.1115/1.4053013

Published Online: May 26, 2022

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Topics: Chemistry, Coolants, Fatigue, Flow (Dynamics), Outflow, Pipes, Pressurized water reactors, Stress, Temperature, Thermal stratification

Journal Articles

Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications

Michio Murase, Yoichi Utanohara, Akio Tomiyama

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031404.

Paper No: NERS-21-1097

DOI: https://doi.org/10.1115/1.4053051

Published Online: May 26, 2022

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Topics: Condensation, Heat transfer, Steam, Temperature, Temperature distribution, Computational fluid dynamics, Mass transfer, Flat plates

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

Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste

Glenn Harvel

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031302.

Paper No: NERS-21-1100

DOI: https://doi.org/10.1115/1.4052808

Published Online: May 26, 2022

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Topics: Fuels, Heat, Nuclear power stations, Plastics, Pyrolysis, Small modular reactors, Heating, Syngas, Temperature, Biochar

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Journal citation

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Manuscript

Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors

Long-Term Performance of Semi-Metallic Gaskets

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

Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating

The Heat Capacity of PuO 2 at High Temperature: Molecular Dynamics Calculations

Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate

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

Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention

The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)

Transient Analysis of Passive Autocatalytic Hydrogen Recombiners Using Computational Fluid Dynamics

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

Thermophysical Characteristics of Liquid Metal In-Bi-Sn Eutectic (Field's Metal) as a Similarity Coolant

Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance

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

Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities

Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications

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

Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste

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