Skip Nav Destination
Issues
April 2023
In Progress
ISSN 2332-8983
EISSN 2332-8975
Research Papers
Thermal Hydraulics and CFD
The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021401.
doi: https://doi.org/10.1115/1.4054546
Topics:
Airfoils
,
Flow (Dynamics)
,
Geometry
,
Stress
,
Heat exchangers
,
Heat transfer
,
Temperature
,
Fluids
,
Structural analysis
Characterization of the Finite Element Computational Fluid Dynamics Capabilities in the Multiphysics Object Oriented Simulation Environment
Abdullah G. Weiss, Laith J. Zaidan, Mohammad T. H. Bani Ahmad, M. Gomaa Abdoelatef, John W. Peterson, Alexander D. Lindsay, Fande Kong, Karim Ahmed, Mark L. Kimber
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021402.
doi: https://doi.org/10.1115/1.4054685
Void Fraction Measurement and Prediction of Two-Phase Boiling Flows in a Tubular Test Section
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021403.
doi: https://doi.org/10.1115/1.4055002
Topics:
Boiling
,
Densitometers
,
Flow (Dynamics)
,
Porosity
,
X-rays
,
Water
,
Flow visualization
,
Two-phase flow
,
Instrumentation
,
Wall temperature
Reactor Physics
Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021501.
doi: https://doi.org/10.1115/1.4053827
Topics:
Design
,
Vessels
,
Cycles
,
Fuels
,
Temperature
,
Fast neutron reactors
,
Small modular reactors
Nuclear Fuels/Cycles and Materials
Validation of Feedback Reactivity Evaluation Models for Plant Dynamics Analysis Code During Unprotected Loss of Heat Sink Event in Sodium-Cooled Fast Reactors
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021601.
doi: https://doi.org/10.1115/1.4055328
Topics:
Feedback
,
Sodium fast reactors
,
Temperature
,
Fuels
,
Sensitivity analysis
,
Density
,
Heat
,
Heat sinks
,
Dynamics (Mechanics)
,
Coolants
Nuclear Safety/Security and Beyond Design Basis Events
Novel Eddy Current Array Sensor Delivery Tool for Automated Nondestructive Examination of Spent Fuel Pool Liner
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021701.
doi: https://doi.org/10.1115/1.4055065
Plant Systems, O&M, and Life Cycle
Experimental Study on Local Damage to Reinforced Concrete Panels Subjected to Oblique Impact by Projectiles
ASME J of Nuclear Rad Sci. April 2023, 9(2): 021801.
doi: https://doi.org/10.1115/1.4054040
Topics:
Damage
,
Impact testing
,
Projectiles
,
Reinforced concrete
Radiation Science
On Cyclotron-Based Production of Gallium-68 Isotope: A Computational Benchmark for the Production Yield & Shielding Considerations
ASME J of Nuclear Rad Sci. April 2023, 9(2): 022001.
doi: https://doi.org/10.1115/1.4055257
Topics:
Cyclotrons
,
Gallium
,
Irradiation (Radiation exposure)
,
Isotopes
,
Particulate matter
,
Protons
,
Uncertainty
Design Innovation Paper
ARKADIA—For the Innovation of Advanced Nuclear Reactor Design
Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Akihiro Uchibori, Takashi Takata, Akiyuki Seki, Yasuhiro Enuma
ASME J of Nuclear Rad Sci. April 2023, 9(2): 025001.
doi: https://doi.org/10.1115/1.4054726
Topics:
Design
,
Optimization
,
Safety
,
Thermal hydraulics
,
Nuclear design
,
Nuclear reactors
,
Computer simulation
Email alerts
RSS Feeds
Improvement of Few-Group Homogenized Cross-Sections for RSG-GAS In-Core Fuel Management Code BATAN-FUEL
ASME J of Nuclear Rad Sci
Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based On RMC
ASME J of Nuclear Rad Sci
Benchmarking Fast Neutrons Leakage Spectrum From Copper Block with 252cf Source in Center
ASME J of Nuclear Rad Sci
