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Research-Article April 9, 2025
Master (Spark Plasma) Sintering Curve of UO2 and UO2-10 vol% Mo Fuel Material
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4068390
Research-Article April 2, 2025
Progress on a Pre-Conceptual Supercritical Water-Cooled Small Modular Reactor
Armando Nava Dominguez, Xianmin Huang, Michel Gaudet, Kittima Khumsa-Ang, Alberto/D'Ansi Mendoza España
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ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4068326
Research-Article March 13, 2025
Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4068167
Technical Briefs January 28, 2025
Investigation of thermal cut-off energy for accurate analysis of High Temperature Engineering Test Reactor
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4067755
Technical Briefs December 21, 2024
Uniform thermal expansion reactivity evaluation based on reactivity coefficient for sodium-cooled fast reactor
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4067483
Research-Article April 30, 2019
RELAP5-3D Simulation of Natural Circulation in Fast Reactors With Lead-Bismuth Eutectic Alloy Coolant
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4036986
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Kinetic Study of Magnetite Precipitation Using a High-Temperature Flow-Through Loop: Experimental Apparatus and Testing Procedure
ASME J of Nuclear Rad Sci (July 2025)
Mechanical Properties and Radon Gas Emanation Analysis of Composite Bricks Reinforced With Cellulose Nanofibrils and Graphene Oxide
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Master (Spark Plasma) Sintering Curve of UO2 and UO2-10 vol% Mo Fuel Material
ASME J of Nuclear Rad Sci
Progress on a Pre-Conceptual Supercritical Water-Cooled Small Modular Reactor
ASME J of Nuclear Rad Sci
Associate Editor's Recognition
ASME J of Nuclear Rad Sci (July 2025)
