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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

Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2

Silja Häkkinen

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041901.

Paper No: NERS-21-1015

DOI: https://doi.org/10.1115/1.4051444

Published Online: March 15, 2022

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Topics: Approximation, Coolants, Cycles, Irradiation (Radiation exposure), Manufacturing, Nuclides, Spent nuclear fuels, Heat, Boron, Photons

Journal Articles

Decay Heat Characterization for the European Sodium Fast Reactor

Antonio Jiménez-Carrascosa, Nuria García-Herranz, Jiri Krepel, Marat Margulis, Una Baker, Eugene Shwageraus, Emil Fridman, Robert Gregg

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011319.

Paper No: NERS-21-1051

DOI: https://doi.org/10.1115/1.4051798

Published Online: October 6, 2021

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Topics: Heat, Cooling

Journal Articles

Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage

Aleksander Grah, Haileyesus Tsige-Tamirat, Joel Guidez, Antoine Gerschenfeld, Konstantin Mikityuk, Janos Bodi, Enrico Girardi

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011314.

Paper No: NERS-20-1204

DOI: https://doi.org/10.1115/1.4051292

Published Online: September 20, 2021

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Topics: Computational fluid dynamics, Concretes, Cooling, Cooling systems, Design, Heat, Heat flux, Leakage, Reactor vessels, Safety

Journal Articles

New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi, Jeremy Bittan, Aleksander Grah, Haileyesus Tsige-Tamirat, Pablo Romojaro, Francisco Álvarez-Velarde, Bernard Carluec

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011312.

Paper No: NERS-20-1080

DOI: https://doi.org/10.1115/1.4051723

Published Online: August 12, 2021

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Topics: Cooling systems, Design, Heat, Heat transfer, Pumps, Safety, Sodium, Sodium fast reactors, Temperature, Vessels

Journal Articles

Evaluation of the Passive Reactor Shutdown System Performance in European Sodium Fast Reactor

Evaldas Bubelis, Michael Schikorr, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011309.

Paper No: NERS-21-1048

DOI: https://doi.org/10.1115/1.4050563

Published Online: August 3, 2021

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Topics: Rods, Sodium fast reactors, Transients (Dynamics), Cooling, Circuits, Flow (Dynamics)

Journal Articles

Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis

Palash K. Bhowmik, J. P. Schlegel, V. Kalra, C. Mills, S. Usman

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031406.

Paper No: NERS-20-1021

DOI: https://doi.org/10.1115/1.4050211

Published Online: April 16, 2021

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Topics: Condensation, Cooling, Design, Flow (Dynamics), Heat transfer, Steam, Test facilities, Temperature, Pressure, Water

Journal Articles

Energy Well: Concept of 20 MW Microreactor Cooled by Molten Salts

Marek Ruščák, Tomáš Melichar, Jan Syblík, Otakar Frýbort, David Harut, Evžen Losa, Martin Mareček, Guido Mazzini, Mathieu Reungoat, Jan Pilát, Marek Benčik, Pavel Král

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021302.

Paper No: NERS-20-1077

DOI: https://doi.org/10.1115/1.4049715

Published Online: February 19, 2021

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Topics: Circuits, Heat, Cooling, Fuels, Safety

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

Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment

Yuliia Filonova, Yaroslav Dubyk, Vladislav Filonov, Vadym Kondratjuk

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011404.

Paper No: NERS-20-1009

DOI: https://doi.org/10.1115/1.4047495

Published Online: October 5, 2020

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Topics: Boundary-value problems, Computational fluid dynamics, Coolants, Flow (Dynamics), Geometry, Temperature, Cooling, Temperature distribution, Metals

Journal Articles

Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

Mahesh Kumar Yadav, Maneesh Punetha, Abhinav Bhanawat, Sameer Khandekar, Pavan K. Sharma

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041108.

Paper No: NERS-19-1164

DOI: https://doi.org/10.1115/1.4046910

Published Online: September 4, 2020

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Topics: Accidents, Condensation, Heat flux, Heat transfer, Pressure, Steady state, Steam, Temperature, Transients (Dynamics), Containment

Journal Articles

Analysis on Critical Factors of Marine Organism Impacts on Water Intake Safety at Nuclear Power Plants

Xiaocheng Fu, Fenglei Du, Xiang Pu, Xuan Wang, Fengze Han

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041101.

Paper No: NERS-19-1110

DOI: https://doi.org/10.1115/1.4048112

Published Online: September 4, 2020

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Topics: Filters, Nuclear power stations, Tides, Water, Cooling, Safety, Design, Seas

Journal Articles

External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET

Kai Kosowski, Marcus Seidl

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021107.

Paper No: NERS-19-1028

DOI: https://doi.org/10.1115/1.4045034

Published Online: January 29, 2020

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Topics: Accidents, Coolants, Cooling, Diesel engines, Emergencies, Flow (Dynamics), Hazards, Heat, Leakage, Pressure

Journal Articles

Advanced Natural Circulation Reduced-Order Model With Inclined Channel for Low Pressure Conditions

René Manthey, Alexander Knospe, Carsten Lange, Christoph Schuster, Antonio Hurtado

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021103.

Paper No: NERS-18-1135

DOI: https://doi.org/10.1115/1.4044846

Published Online: January 29, 2020

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Topics: Pressure, Principal component analysis, Boiling, Stability, Cooling

Journal Articles

RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test

Vincenzo Narcisi, Fabio Giannetti, Andrea Subioli, Alessandro Del Nevo, Gianfranco Caruso

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011301.

Paper No: NERS-19-1001

DOI: https://doi.org/10.1115/1.4044847

Published Online: November 29, 2019

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Topics: Coolants, Flow (Dynamics), Modeling, Pipes, Pumps, Sodium, Temperature, Transients (Dynamics), Vessels, Three-dimensional models

Journal Articles

Suite for Smooth Particle Hydrodynamic Code Relevant to Spherical Plasma Liner Formation and Implosion

Kevin Schillo, Jason Cassibry, Mitchell Rodriguez, Seth Thompson

ASME J of Nuclear Rad Sci. October 2019, 5(4): 042201.

Paper No: NERS-18-1025

DOI: https://doi.org/10.1115/1.4042710

Published Online: July 19, 2019

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Topics: Heat conduction, Particulate matter, Plasmas (Ionized gases), Pressure, Radiation (Physics), Shock (Mechanics), Simulation, Temperature, Viscosity, Vortices

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

Thermal–Hydraulic Design in the Transition Laminar–to–Turbulent Flow Regime

J. Lupiano Contreras, A. S. Doval, P. A. Alberto

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020902.

Paper No: NERS-18-1063

DOI: https://doi.org/10.1115/1.4042363

Published Online: March 15, 2019

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Topics: Design, Flow (Dynamics), Uncertainty, Cooling, Heat transfer coefficients

Journal Articles

The AP1000 Plant and the China Project Commissioning Success

Bryan N. Friedman

ASME J of Nuclear Rad Sci. January 2019, 5(1): 010302.

Paper No: NERS-18-1106

DOI: https://doi.org/10.1115/1.4041973

Published Online: January 24, 2019

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Topics: China, Safety, Cooling, Containment, Heat, Nuclear power stations, Plant design, Design, Accidents

Journal Articles

Analyses of the Costs Associated With Very High Turbine Entry Temperatures in Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants

A. Gad-Briggs, P. Pilidis, T. Nikolaidis

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011019.

Paper No: NERS-18-1020

DOI: https://doi.org/10.1115/1.4041276

Published Online: January 24, 2019

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Topics: Compressors, Cooling, Cycles, Helium, Nuclear power stations, Temperature, Turbines, Gas turbines, Pressure, Turbine blades

Journal citation

NARROW

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

Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2

Decay Heat Characterization for the European Sodium Fast Reactor

Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage

New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment

Evaluation of the Passive Reactor Shutdown System Performance in European Sodium Fast Reactor

Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis

Energy Well: Concept of 20 MW Microreactor Cooled by Molten Salts

Heat Transfer in Induction Melting of Aluminum Oxide in Cold Crucible

Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment

Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

Analysis on Critical Factors of Marine Organism Impacts on Water Intake Safety at Nuclear Power Plants

External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET

Advanced Natural Circulation Reduced-Order Model With Inclined Channel for Low Pressure Conditions

RELAP5-3D Three-Dimensional Analysis Based on PHÉNIX Dissymmetric Transient Test

Suite for Smooth Particle Hydrodynamic Code Relevant to Spherical Plasma Liner Formation and Implosion

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

Thermal–Hydraulic Design in the Transition Laminar–to–Turbulent Flow Regime

The AP1000 Plant and the China Project Commissioning Success

Analyses of the Costs Associated With Very High Turbine Entry Temperatures in Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants

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