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Research-Article September 13, 2024
Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4066523
Research-Article September 2, 2024
TSUNAMI Analyses of the Similarity and Applicability of ZED-2 Critical Experiments for Reactor Physics Code Benchmarking for a Pressurized Water Reactor Small Modular Reactor (PWR-SMR) Design Concept
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4066404
Research-Article August 26, 2024
Heat Flux Correlations for Condensation from Steam and Air Mixtures on Vertical Flat Plates
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4066343
Research-Article August 26, 2024
Radiation Monitoring for Volatilized Zinc Contamination Using Gamma-Ray Imaging and Spectroscopy
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4066342
Research-Article August 26, 2024
Investigation of metal-H2O systems at elevated temperatures: Part III. solubility data and new Zr Pourbaix diagrams at 298.15 K and 373.15 K.
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4066341
Research-Article August 26, 2024
An estimation method for bias error of measurements by utilizing process data, an incidence matrix and a reference instrument for data validation and reconciliation: Part 2 Extension to the energy balance relation
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4066344
Research-Article July 20, 2024
Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in PWR Sub Channel by DNS
ASME J of Nuclear Rad Sci.
doi: https://doi.org/10.1115/1.4066001
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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Investigation of Metal-H2O Systems at Elevated Temperatures: Part II. SnO2(s) Solubility Data and New Sn Pourbaix Diagrams at 298.15 K and 358.15 K
ASME J of Nuclear Rad Sci (April 2025)
Investigation of Metal–H2O Systems at Elevated Temperatures: Part I. Development of a Solubility Apparatus Specialized for Super-Ambient Conditions
ASME J of Nuclear Rad Sci (April 2025)
Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
ASME J of Nuclear Rad Sci
