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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

Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA

Javier Ortiz-Villafuerte, Heriberto Sanchez-Mora, Cesar Queral, Melisa Reyes-Fuentes, Edmundo del-Valle-Gallegos

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1021

DOI: https://doi.org/10.1115/1.4055011

Published Online: July 15, 2022

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Topics: Boiling water reactors, Hydrogen, Uncertainty analysis, Accidents, Simulation, Explosions, Cladding systems (Building), Failure, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations

Journal Articles

Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code

Filip Osuský, Branislav Vrban, Štefan Čerba, Jakub Lüley, Vladimír Nečas

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041401.

Paper No: NERS-21-1012

DOI: https://doi.org/10.1115/1.4051515

Published Online: March 22, 2022

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Topics: Coolants, Design, Fast neutron reactors, Fuels, Heat, Temperature, Transients (Dynamics), Temperature distribution, Simulation, Cladding systems (Building)

Journal Articles

Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code

Jakub Lüley, Branislav Vrban, Štefan Čerba, Filip Osuský, Vladimír Nečas

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041601.

Paper No: NERS-21-1030

DOI: https://doi.org/10.1115/1.4052519

Published Online: March 22, 2022

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Topics: Fuels, Grain size, Irradiation (Radiation exposure), Modeling, Nuclear fission, Rods, Pressure, Cladding systems (Building), Stress

Journal Articles

Concept of a Small Modular SCWR With Horizontal Fuel Assemblies

Thomas Schulenberg, Ivan Otic

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031104.

Paper No: NERS-21-1074

DOI: https://doi.org/10.1115/1.4052191

Published Online: March 15, 2022

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Topics: Coolants, Design, Fuels, Heat, Supercritical water reactors, Water, Temperature, Light water reactors, Cladding systems (Building), Natural convection

Journal Articles

Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

Sami Penttilä, Juha-Matti Autio, Jari Lydman, Aki Toivonen, Seppo Peltonen, Johanna Lukin

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031103.

Paper No: NERS-21-1069

DOI: https://doi.org/10.1115/1.4052974

Published Online: March 15, 2022

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Topics: Cladding systems (Building), Coatings, Fracture (Materials), Fuels, High temperature steam, Pressurized water reactors, Steam, Zirconium, Temperature, Weight (Mass)

Journal Articles

Superphénix Benchmark Part I: Results of Static Neutronics

Alexander Ponomarev, Konstantin Mikityuk, Liang Zhang, Evgeny Nikitin, Emil Fridman, Francisco Álvarez-Velarde, Pablo Romojaro Otero, Antonio Jiménez-Carrascosa, Nuria García-Herranz, Ben Lindley, Una Baker, Armin Seubert, Romain Henry

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011320.

Paper No: NERS-21-1046

DOI: https://doi.org/10.1115/1.4051449

Published Online: October 8, 2021

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Topics: Density, Fuels, Rods, Sodium, Temperature, Steel, Geometry, Cladding systems (Building), Neutrons, Chemical kinetics

Journal Articles

GTAW Welded Inconel 625 Alloy Fuel Cladding for the Canadian SCWR: Microstructure and Mechanical Property Characterization

Cota-Sanchez German, Xiao Lin

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031304.

Paper No: NERS-20-1053

DOI: https://doi.org/10.1115/1.4049278

Published Online: March 16, 2021

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Topics: Heat, Welding, Cladding systems (Building), Fuels, Alloys, Supercritical water reactors, Mechanical properties, Gas tungsten arc welding, Welded joints

Journal Articles

Microstructure and Nanoindentation Studies of Hydridated Zircaloy-4 Claddings After High Temperature Oxidation

Petra Gávelová, Patricie Halodová, Daniela Marušáková, Ondřej Libera, Jakub Krejčí, Věra Vrtílková

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021604.

Paper No: NERS-20-1110

DOI: https://doi.org/10.1115/1.4049053

Published Online: December 14, 2020

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Topics: Cladding systems (Building), High temperature, Hydrogen, Nanoindentation, Oxidation, Oxygen, Temperature, Zirconium, Accidents

Journal Articles

On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application

Marcin Kopeć, Ondřej Pašta, Martina Malá, Patricie Halodová, Ladislav Cvrček, Jakub Krejčí

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021802.

Paper No: NERS-20-1093

DOI: https://doi.org/10.1115/1.4048239

Published Online: November 16, 2020

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Topics: Cladding systems (Building), Coatings, Fuels, Testing, Wear, Wire, Zirconium, Failure, X-rays, Focused ion beams

Journal Articles

Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept

A. Nava Domínguez, Y. F. Rao, T. Beuthe

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031114.

Paper No: NERS-19-1083

DOI: https://doi.org/10.1115/1.4046843

Published Online: June 5, 2020

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Topics: Cladding systems (Building), Coolants, Flow (Dynamics), Fuels, Heat losses, Heat transfer, Manufacturing, Supercritical water reactors, Temperature, Modeling

Journal Articles

About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept

Attila Kiss, Béla Hegyesi, Patrik Richárd Ujváry, András Szabolcs Ványi, Gyula Csom

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031108.

Paper No: NERS-19-1070

DOI: https://doi.org/10.1115/1.4046904

Published Online: June 5, 2020

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Topics: Computational fluid dynamics, Flow (Dynamics), Fluids, Fuels, Manufacturing, Supercritical water reactors, Temperature, Fuel rods, Boundary-value problems, Wire

Journal Articles

Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor

Luis M. Palomino, Mohamed S. El-Genk, Timothy M. Schriener

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031302.

Paper No: NERS-19-1045

DOI: https://doi.org/10.1115/1.4045297

Published Online: March 9, 2020

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Topics: Cladding systems (Building), Emissions, Fuels, Neutrons, Photons, Steel, Vessels, Storage, Radioactivity, Isotopes

Journal Articles

Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards

Yuiko Motome, Yoshiya Akiyama, Hiroyuki Murao

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021115.

Paper No: NERS-19-1073

DOI: https://doi.org/10.1115/1.4045075

Published Online: February 3, 2020

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Topics: Earthquakes, Fuel rods, Fuel storage, Fuels, Radiation (Physics), Safety, Spent fuel storage, Tsunamis, Nuclear fission, Shapes

Journal Articles

From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials

Petra Gávelová, Patricie Halodová, Hygreeva Kiran Namburi, Iveta Adéla Prokůpková, Marek Mikloš, Jakub Krejčí

ASME J of Nuclear Rad Sci. July 2019, 5(3): 030917.

Paper No: NERS-18-1017

DOI: https://doi.org/10.1115/1.4043462

Published Online: May 3, 2019

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Topics: Alloys, High temperature, Oxidation, Testing, Transparency, Zirconium, Creep, Microscopy, Electron backscatter diffraction, Cladding systems (Building)

Journal Articles

Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD

Felix Boldt

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020904.

Paper No: NERS-18-1065

DOI: https://doi.org/10.1115/1.4042118

Published Online: March 15, 2019

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Topics: Cladding systems (Building), Fuel rods, Heat, Hydrogen, Precipitation, Storage, Stress, Temperature, Transients (Dynamics), Simulation

Journal Articles

Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code

Martín Lemes, Alicia Denis, Alejandro Soba

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020903.

Paper No: NERS-18-1078

DOI: https://doi.org/10.1115/1.4042705

Published Online: March 15, 2019

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Topics: Accidents, Cladding systems (Building), Coolants, Fuel rods, Fuels, High temperature, Hydrogen, Simulation, Temperature, Water

Journal Articles

Thermomechanical Safety Analyses for a 238 Pu Production Target at the HFIR

Christopher J. Hurt, James D. Freels, Prashant K. Jain, G. Ivan Maldonado

ASME J of Nuclear Rad Sci. April 2019, 5(2): 021004.

Paper No: NERS-16-1070

DOI: https://doi.org/10.1115/1.4041295

Published Online: March 15, 2019

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Topics: Cycles, Irradiation (Radiation exposure), Safety, Temperature, Stress, Heat transfer, Electrical conductance, Steady state, Heat, Cladding systems (Building)

Journal Articles

Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding

Yangbin Deng, Yingwei Wu, Dalin Zhang, Wenxi Tian, G. H. Su, Suizheng Qiu

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011015.

Paper No: NERS-17-1293

DOI: https://doi.org/10.1115/1.4041194

Published Online: January 24, 2019

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Topics: Accidents, Cladding systems (Building), Fuels, Stress, Pressure, Simulation, Coatings, Zirconium

Journal Articles

New Exploration on TMSR: Redesign of the TMSR Lattice

J. K. Zhao, S. Y. Si, Q. C. Chen, H. Bei

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011008.

Paper No: NERS-17-1187

DOI: https://doi.org/10.1115/1.4041192

Published Online: January 24, 2019

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Topics: Design, Fuels, Graphite, Optimization, Molten salt reactors, Neutrons, Cladding systems (Building), Safety

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Manuscript

Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating

Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA

Development and Processing of Thermal-Hydraulic Model for GFR 2400 Fast Reactor Design and NESTLE Coupled Transient Code

Fuel Performance Modeling at High Burn-Up by FEMAXI-6 Code

Concept of a Small Modular SCWR With Horizontal Fuel Assemblies

Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

Superphénix Benchmark Part I: Results of Static Neutronics

GTAW Welded Inconel 625 Alloy Fuel Cladding for the Canadian SCWR: Microstructure and Mechanical Property Characterization

Microstructure and Nanoindentation Studies of Hydridated Zircaloy-4 Claddings After High Temperature Oxidation

On Debris-Fretting Impact—The Study of Oxide and Chromium Layer Application

Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept

About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept

Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor

Evaluation of Radiation Effects on Residents Living Around the NSRR Under External Hazards

From Micro to Nano: Material Characterization Methods for Testing of Nuclear Core and Structural Materials

Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD

Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code

Thermomechanical Safety Analyses for a 238 Pu Production Target at the HFIR

Simulation on Pellet–Cladding Mechanical Interaction of Accident Tolerant Fuel With Coated Cladding

New Exploration on TMSR: Redesign of the TMSR Lattice

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