Skip Nav Destination
Just Accepted Manuscript
Research-Article September 30, 2023
Advancement Towards the Experimental Measurement of the Lbe Thermal Properties Using DSC Technique
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4063572
Research-Article September 11, 2023
Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts with a Hydrogen-based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4063388
Research-Article August 30, 2023
On Frequency / Time Invariance of Certain Temporal and Complex Transfer Functions for the 1d Interfacial Monochromatic Neutron Density Wave
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4063291
Research-Article August 24, 2023
Experimental Study Of Helium Stratification In Multi-Compartment Containment Studies Facility
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4063239
Research-Article August 24, 2023
“Development And Testing Of A System Thermal-Hydraulics Model For A 50-Mwel-Class Pressurized Water Reactor - Small Modular Reactor (Pwr-Smr)”
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4063240
Research-Article August 11, 2023
Thermomechanical Performance Assessment of U-Mo Monolithic Fuel Plates with Zircaloy Cladding
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4063163
Research-Article August 11, 2023
Survey Analysis of Potential Nuclear Safety Research of Thailand for International Research Collaborative Reinforcement in the 2020s
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4063162
Review Articles August 5, 2023
Development Of Analysis Tools For Heat Pipes Used In Small Modular Reactors: Sodium Property Correlations
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4063112
Research-Article August 5, 2023
Depletion Calculations For An Integral Small Molten Salt Reactor With Serpent
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4063111
Research-Article July 25, 2023
Study of γ-ray Spectrum Measurement Analysis Algorithm of Radioactive Solid Waste Steel Boxes
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4063039
Technical Briefs July 21, 2023
CFD Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4063007
Research-Article July 21, 2023
Total Loss of Feedwater Analysis of PWR Using RELAP5
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4063009
Research-Article July 7, 2023
Implementation Of Solar Salt Properties Into Ariant And Simulation Of Pressurized Loss Of Forced Circulation In A High Temperature Gas-Cooled Small Modular Reactor
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4062917
Research-Article June 20, 2023
Interactions Between Molten Sodium and Standard Pipe Insulation
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4062798
Research-Article June 20, 2023
Dose Rate Assessment Around the PCFV Release Line During Severe Accident Conditions in Nuclear Power Plant Krsko
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4062797
Research-Article June 20, 2023
Uncertainty and Sensitivity Evaluation of the QUENCH-02 Experiment Simulation Using the ASYST Code
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4062799
Research-Article June 16, 2023
Development of Analysis Tools for Heat Pipes Used in the Core Cooling of Small Modular Reactors: Potassium Property Correlations
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4062752
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 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
Email alerts
RSS Feeds
Advancement Towards the Experimental Measurement of the Lbe Thermal Properties Using DSC Technique
ASME J of Nuclear Rad Sci
9 MV LINAC Photoneutron Interrogation of Uranium With Advanced Acoustically Tensioned Metastable Fluid Detectors
ASME J of Nuclear Rad Sci (October 2023)
Study on the Step by Step Process and Performance of Laser Welding for the Spent Fuel Pool Floor
ASME J of Nuclear Rad Sci (October 2023)
Linear and Nonlinear Stability Analysis of Molten Salt Natural Circulation Loop
ASME J of Nuclear Rad Sci (October 2023)
Experimental Analysis of Bubble Behavior and Critical Heat Flux During Pool Boiling on Vertical Circular Tubes
ASME J of Nuclear Rad Sci (October 2023)
