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Issues
October 2023
ISSN 2332-8983
EISSN 2332-8975
Special Papers
Effect of Niobium on Sintering Process of Gamma Phase Uranium Alloys Fuel Pellets
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041101.
doi: https://doi.org/10.1115/1.4062795
Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications
Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041102.
doi: https://doi.org/10.1115/1.4056854
Topics:
Coolants
,
Flow (Dynamics)
,
Fuels
,
Sodium
,
Temperature
,
Accidents
,
Transients (Dynamics)
,
Pins (Engineering)
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, 9(4): 041103.
doi: https://doi.org/10.1115/1.4056772
Topics:
Coolants
,
Design
,
Diluents
,
Fuels
,
Leakage
,
Neutrons
,
Supercritical carbon dioxide
,
Nuclear fission
,
Nuclides
,
Feedback
Neutronic and Thermal-Fluidic Analyses for an Additive Manufactured Reactor With SiC Matrix and TRISO Particle Fuel
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041104.
doi: https://doi.org/10.1115/1.4062119
Topics:
Additive manufacturing
,
Computational fluid dynamics
,
Design
,
Fuels
,
Particulate matter
,
Temperature
,
Coolants
,
Neutrons
,
Heat transfer
,
Computer software
Study on Performance of New Flexible Shielding Materials and First Demonstration Application in Chinese Pressurized Water Reactor Nuclear Power Plant
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041105.
doi: https://doi.org/10.1115/1.4062796
Main Parameters Influencing the Level of Labile Contamination and the Removal Factor
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041106.
doi: https://doi.org/10.1115/1.4062550
Topics:
Contamination
,
Surface roughness
,
Pressure
,
Temperature
,
Drying
A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041107.
doi: https://doi.org/10.1115/1.4062879
Topics:
Molten salt reactors
,
Simulation
,
Wall thickness
,
Safety
,
Computer simulation
,
Design
,
Temperature
,
Heat conduction
,
Melting
,
Solidification
ATHENA Main Heat Exchanger Conceptual Design and Thermal-Hydraulic Assessment With RELAP5 Code
Tommaso Del Moro, Pierdomenico Lorusso, Fabio Giannetti, Mariano Tarantino, Marco Caramello, Daniele Mazzi, Marin Constantin
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041108.
doi: https://doi.org/10.1115/1.4056973
Topics:
Cycles
,
Heat exchangers
,
Sensitivity analysis
,
Water
,
Fast neutron reactors
,
Conceptual design
,
Temperature
,
Heat
,
Bathythermographs
,
Geometry
Hydrogen Loading System for Thin Films for Betavoltaics
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041109.
doi: https://doi.org/10.1115/1.4056974
Topics:
Hydrogen
,
Palladium
,
Temperature
,
Leakage
,
Pressure drop
,
Thin films
Research Papers
Next Generation/Advanced Reactors
Eddy Current Flow Meter Measurements in Liquid Sodium at High Temperatures
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041301.
doi: https://doi.org/10.1115/1.4062239
Topics:
Eddies (Fluid dynamics)
,
Flow (Dynamics)
,
Flowmeters
,
High temperature
,
Sensors
,
Sodium
,
Temperature
,
Wire
,
Eddy currents (Electricity)
,
Liquid metals
System Thermal-Hydraulics Model for Fluoride Salt-Cooled Reactor Based on Small Modular Advanced High Temperature Reactor (SmAHTR) Design Concept
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041302.
doi: https://doi.org/10.1115/1.4062500
Topics:
Coolants
,
Cycles
,
Design
,
Flow (Dynamics)
,
Fuels
,
High temperature
,
Modeling
,
Temperature
,
Thermal hydraulics
,
Steady state
Thermal Hydraulics and CFD
Linear and Nonlinear Stability Analysis of Molten Salt Natural Circulation Loop
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041401.
doi: https://doi.org/10.1115/1.4063040
Topics:
Stability
Experimental Analysis of Bubble Behavior and Critical Heat Flux During Pool Boiling on Vertical Circular Tubes
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041402.
doi: https://doi.org/10.1115/1.4063041
Topics:
Bubbles
,
Critical heat flux
,
Dimensions
,
Pool boiling
Nuclear Safety/Security and Beyond Design Basis Events
Comparative Maps of Safety Features for Fission and Fusion Reactors
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041701.
doi: https://doi.org/10.1115/1.4062643
Topics:
Fusion reactors
,
Nuclear fission
,
Safety
,
Hazards
Plant Systems, O&M, and Life Cycle
Experimental Investigation of Control Rod Drops Into Perturbed Fuel Assemblies
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041801.
doi: https://doi.org/10.1115/1.4062275
Topics:
Deformation
,
Fuels
,
Manufacturing
,
Impact testing
,
Buckling
An Estimation Method for Bias Error of Measurements by Utilizing Process Data, An Incidence Matrix and a Reference Instrument for Data Validation and Reconciliation
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041802.
doi: https://doi.org/10.1115/1.4062865
Topics:
Errors
,
Flow (Dynamics)
,
Instrumentation
,
Measurement uncertainty
,
Uncertainty
,
Nuclear power stations
,
Sensors
,
Pipes
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, 9(4): 041803.
doi: https://doi.org/10.1115/1.4063008
Topics:
Ferrites (Magnetic materials)
,
Laser welding
,
Spent nuclear fuels
,
Water
,
Welding
,
Maintenance
,
Corrosion
,
Steel
,
High pressure (Physics)
,
Stainless steel
Radiation Science
9 MV LINAC Photoneutron Interrogation of Uranium With Advanced Acoustically Tensioned Metastable Fluid Detectors
ASME J of Nuclear Rad Sci. October 2023, 9(4): 042001.
doi: https://doi.org/10.1115/1.4062951
Technical Brief
Small Modular Reactors: Opportunities and Challenges as Emerging Nuclear Technologies for Power Production
ASME J of Nuclear Rad Sci. October 2023, 9(4): 044501.
doi: https://doi.org/10.1115/1.4062644
Topics:
Design
,
Safety
,
Small modular reactors
,
Fuels
Email alerts
RSS Feeds
Operation Optimization Framework for Advanced Reactors Using a Data-Driven Digital Twin
ASME J of Nuclear Rad Sci (April 2025)
Numerical Analysis of Gas Generation and Migration in a Radioactive Waste Disposal Cell of a Deep Geological Repository
ASME J of Nuclear Rad Sci (April 2025)
Investigating the Suitability of Cu2ZnSnS4 Thin Films for Gamma Radiation Dosimetry Applications in Nonmedical Environments
ASME J of Nuclear Rad Sci (April 2025)