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Research-Article May 27, 2023
Fabrication Aspects and Performance Characterization of α-Al2O3/ALPO4 Based Sandwich Configuration Flow Channel Inserts and Coatings for High Temperature Liquid Metal Applications
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4062646
Research-Article May 27, 2023
Comparative Maps of Safety Features for Fission and Fusion Reactors
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4062643
Technical Briefs May 27, 2023
Small Modular Reactors: Opportunities and Challenges as Emerging Nuclear Technologies for Power Production
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4062644
Research-Article May 5, 2023
System Thermal-hydraulics Model for Fluoride Salt-Cooled Reactor Based On Small Advanced High Temperature Reactor (smAHTR) Design Concept
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4062500
Research-Article April 6, 2023
Experimental Investigation of Control Rod Drops into Perturbed Fuel Assemblies
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4062275
Research-Article March 31, 2023
Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4062239
Research-Article July 15, 2022
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.
doi: https://doi.org/10.1115/1.4055011
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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Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code
ASME J of Nuclear Rad Sci (October 2023)
Main Parameters Influencing the Level of Labile Contamination and the Removal Factor
ASME J of Nuclear Rad Sci (October 2023)
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ASME J of Nuclear Rad Sci (July 2023)
Comparative Maps of Safety Features for Fission and Fusion Reactors
ASME J of Nuclear Rad Sci