Topics: Coatings , Engineering prototypes , Flow (Dynamics) , High temperature , Insulation , Liquid metals , Magnetohydrodynamics , Manufacturing , Pressure , Welding

Technical Brief: Safeguardability Analysis of a Molten Salt Sampling System Design

Megan Harkema, Steven Krahn, Paul Marotta

ASME J of Nuclear Rad Sci. July 2024, 10(3): 030903. doi: https://doi.org/10.1115/1.4064343

Abstracts

View articletitled, Technical Brief: Safeguardability Analysis of a Molten Salt Sampling System Design

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Topics: Design , Fuels , Molten salt reactors , Engineering prototypes

Public–Private Partnering in Nuclear Reactor Development—Historical Review and Implications for Today

Steven Krahn, Andrew Sowder

ASME J of Nuclear Rad Sci. July 2024, 10(3): 030904. doi: https://doi.org/10.1115/1.4064233

Abstracts

View articletitled, Public–Private Partnering in Nuclear Reactor Development—Historical Review and Implications for Today

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Topics: Construction , Governments , Nuclear power , Nuclear reactors , Technology development , Boiling water reactors , Pressurized water reactors , Design

Implementation of Solar Salt Properties Into ARIANT and Simulation of Pressurized Loss of Forced Circulation in a High Temperature Gas-Cooled Small Modular Reactor

Jason H. Wu, Thomas G. Beuthe, Aleksandar Vasić

ASME J of Nuclear Rad Sci. July 2024, 10(3): 030905. doi: https://doi.org/10.1115/1.4062917

Abstract

View articletitled, Implementation of Solar Salt Properties Into ARIANT and Simulation of Pressurized Loss of Forced Circulation in a High Temperature Gas-Cooled Small Modular Reactor

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Topics: Heat , Simulation , Solar energy , Temperature , High temperature , Helium , Fuels , Coolants , Fluids , Small modular reactors

Electrochemical Activity Measurements of UCl₃ in Molten NaCl-MgCl₂-UCl₃

Jacob Yankey, Marisa Monreal, Matt Jackson, Michael Simpson

ASME J of Nuclear Rad Sci. July 2024, 10(3): 030906. doi: https://doi.org/10.1115/1.4064598

Abstracts

View articletitled, Electrochemical Activity Measurements of UCl3 in Molten NaCl-MgCl2-UCl3

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Topics: Circuits , Electrodes , Molten salt reactors , Temperature , Zirconium , Electrodeposition , Rods , Electrons

Design and Analysis of a Free-Piston Stirling Engine for Microreactor Applications

Phat Doan, Minghui Chen

ASME J of Nuclear Rad Sci. July 2024, 10(3): 030907. doi: https://doi.org/10.1115/1.4064335

Abstracts

View articletitled, Design and Analysis of a Free-Piston Stirling Engine for Microreactor Applications

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Topics: Design , Engines , Pistons , Pressure , Stirling engines , Temperature , Compression , Matlab

Molten Salt Pump Journal-Bearings Dynamic Characteristics Under Hydrodynamic Lubrication Conditions

Yuqi Liu, Minghui Chen, Shuai Che, Adam Burak

ASME J of Nuclear Rad Sci. July 2024, 10(3): 030908. doi: https://doi.org/10.1115/1.4064336

Abstracts

View articletitled, Molten Salt Pump Journal-Bearings Dynamic Characteristics Under Hydrodynamic Lubrication Conditions

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Topics: Bearings , Journal bearings , Lubrication , Pumps , Damping , Stiffness , High temperature

RESEARCH PAPERS

Next Generation/Advanced Reactors

Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume

R. Andika Putra Dwijayanto, Harun Ardiansyah, Andang Widi Harto

ASME J of Nuclear Rad Sci. July 2024, 10(3): 031301. doi: https://doi.org/10.1115/1.4064465

Abstracts

View articletitled, Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume

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Topics: Fluids , Fuels , Geometry , Molten salt reactors , Neutrons , Optimization , Temperature

Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods

Daniel T. Wojtaszek, Blair P. Bromley

ASME J of Nuclear Rad Sci. July 2024, 10(3): 031302. doi: https://doi.org/10.1115/1.4064581

Abstracts

View articletitled, Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods

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Topics: Fuels , Hydrogen , Temperature , Very high temperature reactors , Uranium , Manufacturing

Thermal Hydraulics and CFD

An Improved Heat Flux Partitioning Model of Nucleate Boiling Under Saturated Pool Boiling Condition

Mingfu He, Minghui Chen

ASME J of Nuclear Rad Sci. July 2024, 10(3): 031401. doi: https://doi.org/10.1115/1.4064337

Abstracts

View articletitled, An Improved Heat Flux Partitioning Model of Nucleate Boiling Under Saturated Pool Boiling Condition

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Topics: Bubbles , Dynamics (Mechanics) , Heat flux , Heat transfer , Nucleate boiling , Pool boiling , Boiling , Nucleation (Physics) , Quenching (Metalworking) , Critical heat flux

Reactor Physics

Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries

Thanh Mai Vu, Le Quang Linh Tran, Thi Hong Bui, Nhu Viet Ha Pham

ASME J of Nuclear Rad Sci. July 2024, 10(3): 031501. doi: https://doi.org/10.1115/1.4064780

Abstracts

View articletitled, Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries

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Topics: Eigenvalues , Fast neutron reactors , Neutrons , Nuclear fission , Nuclear reactors , Uncertainty , Uncertainty analysis , Cross section (Physics) , Electromagnetic scattering , Radiation scattering

Nuclear Fuels/Cycles and Materials

Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development

Jason L. Schulthess, Katelyn Baird, Philip Petersen, Daniele Salvato, Hakan Ozaltun, William A. Hanson, Nicholas Ullum, Jeffrey Giglio, James I. Cole

ASME J of Nuclear Rad Sci. July 2024, 10(3): 031601. doi: https://doi.org/10.1115/1.4064779

Abstracts

View articletitled, Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development

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Topics: Bending strength , Density , Fuels , Mechanical properties , Nuclear fission , Porosity , Stress , Young's modulus , Zirconium , Alloys

Nuclear Safety/Security and Beyond Design Basis Events

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

Javier Ortiz-Villafuerte, Heriberto Sánchez-Mora, César Queral, Melisa Reyes-Fuentes, Edmundo del- Valle-Gallegos

ASME J of Nuclear Rad Sci. July 2024, 10(3): 031701. doi: https://doi.org/10.1115/1.4055011

Abstract

View articletitled, Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a Boiling Water Reactor STSBO Using MAAP5 and AZTUSIA

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Topics: Boiling water reactors , Hydrogen , Oxidation , Simulation , Uncertainty analysis , Zirconium , Accidents , Sensitivity analysis , Temperature , Uncertainty

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SPECIAL SECTION: PROGRESS IN ADVANCED NUCLEAR REACTORS

SPECIAL PAPERS

Interactions Between Molten Sodium and Standard Pipe Insulation

Fabrication Aspects and Performance Characterization of α-Al₂O₃/AlPO₄ Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications

Technical Brief: Safeguardability Analysis of a Molten Salt Sampling System Design

Public–Private Partnering in Nuclear Reactor Development—Historical Review and Implications for Today

Implementation of Solar Salt Properties Into ARIANT and Simulation of Pressurized Loss of Forced Circulation in a High Temperature Gas-Cooled Small Modular Reactor

Electrochemical Activity Measurements of UCl₃ in Molten NaCl-MgCl₂-UCl₃

Design and Analysis of a Free-Piston Stirling Engine for Microreactor Applications

Molten Salt Pump Journal-Bearings Dynamic Characteristics Under Hydrodynamic Lubrication Conditions

RESEARCH PAPERS

Next Generation/Advanced Reactors

Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume

Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods

Thermal Hydraulics and CFD

An Improved Heat Flux Partitioning Model of Nucleate Boiling Under Saturated Pool Boiling Condition

Reactor Physics

Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries

Nuclear Fuels/Cycles and Materials

Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development

Nuclear Safety/Security and Beyond Design Basis Events

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

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SPECIAL SECTION: PROGRESS IN ADVANCED NUCLEAR REACTORS

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