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Issues
April 2024
ISSN 2332-8983
EISSN 2332-8975
Review Article
Development of Analysis Tools for Heat Pipes Used in Small Modular Reactors: Sodium Property Correlations
ASME J of Nuclear Rad Sci. April 2024, 10(2): 020801.
doi: https://doi.org/10.1115/1.4063112
Topics:
Sodium
,
Temperature
,
Vapors
,
Heat pipes
Research Papers
Next Generation/Advanced Reactors
Depletion Calculations for an Integral Small Molten Salt Reactor With Serpent
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021301.
doi: https://doi.org/10.1115/1.4063111
Topics:
Fuels
,
Molten salt reactors
,
Flow (Dynamics)
,
Cycles
,
Nuclear fission
Advancement Toward the Experimental Measurement of the Lead–Bismuth Eutectic Thermal Properties Using Differential Scanning Calorimetry Technique
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021302.
doi: https://doi.org/10.1115/1.4063572
Topics:
Calibration
,
Differential scanning calorimetry
,
Heating
,
Latent heat
,
Melting
,
Melting point
,
Specific heat
,
Temperature
,
Thermal properties
,
Uncertainty
Thermal Hydraulics and CFD
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. April 2024, 10(2): 021401.
doi: https://doi.org/10.1115/1.4062752
Topics:
Potassium
,
Temperature
,
Vapors
,
Heat pipes
Development and Testing of a System Thermal-Hydraulics Model for a 50-MWel-Class Pressurized Water Reactor–Small Modular Reactor
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021402.
doi: https://doi.org/10.1115/1.4063240
Topics:
Boilers
,
Design
,
Flow (Dynamics)
,
Pressure
,
Pressurized water reactors
,
Small modular reactors
,
Temperature
,
Thermal hydraulics
,
Oscillations
,
Junctions
Reactor Physics
On Frequency/Time Invariance of Certain Temporal and Complex Transfer Functions for the One-Dimensional Interfacial Monochromatic Neutron Density Wave
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021501.
doi: https://doi.org/10.1115/1.4063291
Topics:
Density
,
Neutrons
,
Transfer functions
,
Waves
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. April 2024, 10(2): 021502.
doi: https://doi.org/10.1115/1.4063388
Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021503.
doi: https://doi.org/10.1115/1.4063739
Topics:
Control systems
,
Design
,
Fast neutron reactors
,
Fuels
,
Neutrons
,
Rods
,
Coolants
,
Boron
,
Absorption
,
Safety
Nuclear Fuels/Cycles and Materials
Thermomechanical Performance Assessment of U-Mo Monolithic Fuel Plates With Zircaloy Cladding
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021601.
doi: https://doi.org/10.1115/1.4063163
Neutronic Analysis and Fuel Cycle Parameters of Transuranic-UO2 Fueled Dual Cooled VVER-1000 Assembly
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021602.
doi: https://doi.org/10.1115/1.4063757
Topics:
Cycles
,
Fuel rods
,
Fuels
,
Manufacturing
,
Neutron flux
,
Neutrons
,
Nuclear fission
,
Nuclear fuel cycle
,
Rods
,
Safety
Nuclear Safety/Security and Beyond Design Basis Events
Experimental Study of Helium Stratification in Multi-Compartment Containment Studies Facility
Bhuvaneshwar Gera, Pavan K. Sharma, Aditya Karanam, Shubham Mishra, I. Thangamani, Nandan Saha, Anu Dutta, Priyanshu Goyal, Vishnu Verma, Jayanta Chattopadhyay
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021701.
doi: https://doi.org/10.1115/1.4063239
Topics:
Containment
,
Errors
,
Helium
,
Hydrogen
Application of Level 3 Probabilistic Safety Analysis in UK HPR1000
ASME J of Nuclear Rad Sci. April 2024, 10(2): 021702.
doi: https://doi.org/10.1115/1.4063874
Topics:
Accidents
,
Radiation (Physics)
,
Risk
,
Probabilistic safety assessment
,
Design
Code and Regulatory Issues
Technical Evaluation Requirements on Welding-Related Nonconformance Reports
ASME J of Nuclear Rad Sci. April 2024, 10(2): 022101.
doi: https://doi.org/10.1115/1.4063630
Topics:
Welding
,
Construction
,
Design
Technical Brief
Cold Crucible Facility for Severe Accident Research at Canadian Nuclear Laboratories
ASME J of Nuclear Rad Sci. April 2024, 10(2): 024501.
doi: https://doi.org/10.1115/1.4063673
Topics:
Accidents
,
Zirconium
,
Electromagnetic induction
Email alerts
RSS Feeds
Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in Pressurized Water Reactor Sub Channel by Direct Numerical Simulation
ASME J of Nuclear Rad Sci (April 2025)
Heat Flux Correlations for Condensation From Steam and Air Mixtures on Vertical Flat Plates
ASME J of Nuclear Rad Sci (April 2025)
Radiation Monitoring for Volatilized Zinc Contamination Using Gamma-Ray Imaging and Spectroscopy
ASME J of Nuclear Rad Sci (April 2025)
Operation Optimization Framework for Advanced Reactors Using a Data Driven Digital Twin
ASME J of Nuclear Rad Sci
