Skip Nav Destination
Issues
October 2024
ISSN 2332-8983
EISSN 2332-8975
Review Articles
Revenue Requirements Method for Assessing the Cost Impact of Fuel Cladding Corrosion in a Supercritical Water-Cooled Small Modular Reactor: A Methodological Review on Life Cycle Costing Corrosion
ASME J of Nuclear Rad Sci. October 2024, 10(4): 040801.
doi: https://doi.org/10.1115/1.4064639
Topics:
Cladding systems (Building)
,
Corrosion
,
Fuels
,
Supercritical water reactors
,
Water
Practical Approach to Nuclear Shelter Wall Thickness Estimation
ASME J of Nuclear Rad Sci. October 2024, 10(4): 040802.
doi: https://doi.org/10.1115/1.4065463
Topics:
Concretes
,
Gamma rays
,
Neutrons
,
Nuclear fission
,
Wall thickness
,
Bombs
Reviewing Welding Procedures—Checklists for Nuclear Power Systems
ASME J of Nuclear Rad Sci. October 2024, 10(4): 040803.
doi: https://doi.org/10.1115/1.4065851
Topics:
Welding
,
Nuclear power
,
Design
,
ASME Boiler and Pressure Vessel Code
Research Paper
The Transfer of Xenon-135 to Molten Salt Reactor Graphite
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041001.
doi: https://doi.org/10.1115/1.4064464
Topics:
Graphite
,
Porosity
,
Fuels
,
Molten salt reactors
,
Mass transfer
,
Diffusion (Physics)
Research Papers
Reactor Physics
Effect of Radial Neutron Reflector on the Characteristics of Nuclear Fuel Burn-Up Wave in a Fast Neutron Energy Spectrum Multiplying Medium: A Consistent Parametric Approach
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041501.
doi: https://doi.org/10.1115/1.4065893
Topics:
Diffusion (Physics)
,
Fuels
,
Geometry
,
Neutron flux
,
Neutrons
,
Scalars
,
Waves
,
Nuclear fuels
,
Design
,
Transients (Dynamics)
Nuclear Fuels/Cycles and Materials
Monitoring for Actinide Neutron Emissions From Spent Nuclear Fuel Under Extreme Gamma Fields Using Centrifugally Tensioned Metastable Fluid Detector Sensor Technology
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041601.
doi: https://doi.org/10.1115/1.4065280
Nuclear Safety/Security and Beyond Design Basis Events
Validation Assessment of Turbulent Reacting Flow Model Using the Area-Validation Metric on Medium-Scale Methanol Pool Fire Results
ASME J of Nuclear Rad Sci. October 2024, 10(4): 041701.
doi: https://doi.org/10.1115/1.4065173
Topics:
Fire
,
Flames
,
Flow (Dynamics)
,
Heat flux
,
Liquid pool fires
,
Methanol
,
Simulation
,
Temperature
,
Turbulence
,
Combustion
Radiation Science
Performance of NB-CTMFD Detector Versus Ludlum 42-49B, and Fuji NSN3 Detectors for Hard (Am-Be) and Soft (Cf-252 Fission) Energy Spectra Neutron Sources Within Lead/Concrete Shielded Configurations
ASME J of Nuclear Rad Sci. October 2024, 10(4): 042001.
doi: https://doi.org/10.1115/1.4065852
Topics:
Concretes
,
Fluids
,
Neutrons
,
Sensors
,
Particulate matter
,
Neutron sources
,
Nuclear fission
,
Spectra (Spectroscopy)
,
Simulation
Performance of Borated Centrifugally Tensioned Metastable Fluid Detector Versus Ludlum 42-49B, Fuji NSN3 Detectors for Fission Energy Spectrum Neutron Detection With the Source Within Lead/Concrete Shielded Configurations
ASME J of Nuclear Rad Sci. October 2024, 10(4): 042002.
doi: https://doi.org/10.1115/1.4065853
Topics:
Concretes
,
Fluids
,
Neutrons
,
Sensors
,
Nuclear fission
Technical Brief
Modeling of N and P-Type of Coaxial Ge Detectors Using MCNPX and the Effect of Dead Layer Variation on Its Response Function
ASME J of Nuclear Rad Sci. October 2024, 10(4): 044501.
doi: https://doi.org/10.1115/1.4065395
Topics:
Sensors
,
Simulation
,
Dimensions
Email alerts
RSS Feeds
Operation Optimization Framework for Advanced Reactors Using a Data Driven Digital Twin
ASME J of Nuclear Rad Sci
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 (April 2025)
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
