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Issues
January 2021
ISSN 2332-8983
EISSN 2332-8975
In this Issue
Editorial
Editorial
ASME J of Nuclear Rad Sci. January 2021, 7(1): 010201.
doi: https://doi.org/10.1115/1.4048722
Topics:
Nuclear engineering
,
Radiation (Physics)
,
China
Reviewer's Recognition
ASME J of Nuclear Rad Sci. January 2021, 7(1): 010202.
doi: https://doi.org/10.1115/1.4049098
Topics:
Cities
ASME Nuclear Engineering Division Chair's Message
ASME J of Nuclear Rad Sci. January 2021, 7(1): 010203.
doi: https://doi.org/10.1115/1.4048762
Topics:
Nuclear engineering
Greetings From JSME PESD
ASME J of Nuclear Rad Sci. January 2021, 7(1): 010204.
doi: https://doi.org/10.1115/1.4048721
Message From Shoujun Wang, Chinese Nuclear Society President
ASME J of Nuclear Rad Sci. January 2021, 7(1): 010205.
doi: https://doi.org/10.1115/1.4048634
Review Article
The Intersection of Advancing Technology and Human Performance
ASME J of Nuclear Rad Sci. January 2021, 7(1): 010801.
doi: https://doi.org/10.1115/1.4047717
Topics:
Errors
,
Machinery
,
Human factors
,
Design
Research Papers
Next Generation/Advanced Reactors
Study on Melt Coolability and Water Ingression Through Melt Pool in Scaled Down Core Catcher—The Influence of Vessel Angle
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011301.
doi: https://doi.org/10.1115/1.4048235
Topics:
Temperature
,
Vessels
,
Water
Thermal Hydraulics and CFD
Flow Instability Investigation at Supercritical Pressures in Parallel Channels by Computational Fluid Dynamics Adopting Low- and High-Power Boundaries
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011401.
doi: https://doi.org/10.1115/1.4046255
Topics:
Computational fluid dynamics
,
Flow (Dynamics)
,
Flow instability
,
Gravity (Force)
,
Oscillations
,
Pressure
,
Temperature
,
Heating
,
Turbulence
,
Coolants
Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011402.
doi: https://doi.org/10.1115/1.4047161
Topics:
Accidents
,
Boiling water reactors
,
Eigenvalues
,
Fluids
,
Porosity
,
Pressure
,
Pressurized water reactors
,
Light water reactors
,
Water
,
Stability
Experimental Investigation of Flow Instability Between Two Vertical Parallel Channels Using Supercritical CO2
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011403.
doi: https://doi.org/10.1115/1.4047716
Topics:
Electricity (Physics)
,
Flow (Dynamics)
,
Flow instability
,
Heating
,
Pressure
,
Temperature
,
Fluids
,
Oscillations
,
Valves
,
Carbon dioxide
Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011404.
doi: https://doi.org/10.1115/1.4047495
Reactor Physics
Total Cross Section Phenomenological Formulas for X-Ray and Gamma Radiation Interaction With Matter for Different Energies and Absorber Types
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011501.
doi: https://doi.org/10.1115/1.4045806
Topics:
Approximation
,
Gamma rays
,
Photons
,
Polynomials
,
Radiation (Physics)
,
X-rays
,
Absorption spectra
,
Photoelectric effect
A Simplified Two-Group Multipoint Kinetics Model
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011502.
doi: https://doi.org/10.1115/1.4046254
Topics:
Eigenvalues
,
Heat flux
,
Neutrons
,
Steady state
,
Transients (Dynamics)
,
Thermal hydraulics
,
Diffusion (Physics)
,
Simulation
,
Circuits
,
Fluid dynamics
Nuclear Fuels/Cycles and Materials
The Other Metallic Phase in Spent Nuclear Fuel: A Complete Thermodynamic Evaluation of the U–Pd–Rh–Ru System
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011601.
doi: https://doi.org/10.1115/1.4046784
Topics:
Nuclear fuels
,
Phase diagrams
,
Temperature
,
Uranium
,
Modeling
,
Military systems
,
Nuclear fission
,
Spent nuclear fuels
Ni+ and He+ Implantation Effects on the Hardness and Microstructure of Heat-Treated X750 Superalloy
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011602.
doi: https://doi.org/10.1115/1.4046716
Topics:
Alloys
,
Damage
,
Electron microscopy
,
Hardening
,
Heat
,
Helium
,
Ion implantation
,
Irradiation (Radiation exposure)
,
Superalloys
,
Testing
Preparation and Characterization of Nb-1Zr-0.1C Alloy Suitable for Liquid Metal Coolant Channels of High Temperature Reactors
S. Majumdar, J. Kishor, A. N. Behera, B. Vishwanadh, A. Borgohain, R. Kapoor, R. Tewari, V. Kain, Madangopal Krishnan, G. K. Dey, S. Banerjee
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011603.
doi: https://doi.org/10.1115/1.4047919
Topics:
Alloys
,
Creep
,
Errors
,
Cathode ray oscilloscopes
,
Electron beams
,
High temperature
,
Corrosion
,
Melting
Toward a Mechanistic Model of Stress Corrosion Cracking in PHWR Fuel Sheaths
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011604.
doi: https://doi.org/10.1115/1.4048120
Topics:
Failure
,
Fracture (Materials)
,
Fuels
,
Nuclear fission
,
Diffusion (Physics)
Calculation of Dynamical Phase Diagram in U-Zr Binary System Under Irradiation
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011605.
doi: https://doi.org/10.1115/1.4047718
Nuclear Safety/Security and Beyond Design Basis Events
Study on Description of Plant Status at Fukushima Accident by Emergency Action Level
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011701.
doi: https://doi.org/10.1115/1.4046841
Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011702.
doi: https://doi.org/10.1115/1.4046257
Topics:
Pipes
,
Temperature
,
Vessels
,
Heavy water reactors
Finite Element Model of a Melting Terminal Debris Bed in a CANDU Calandria
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011703.
doi: https://doi.org/10.1115/1.4048008
Topics:
Accidents
,
Finite element model
,
Heat
,
Melting
,
Porosity
,
Temperature
,
Transients (Dynamics)
,
Uranium
,
Materials properties
Plant Systems, O&M, and Life Cycle
Unequivocally Nonconservative Results From One Method of Imperfection Quantification in RCC-MR
ASME J of Nuclear Rad Sci. January 2021, 7(1): 011801.
doi: https://doi.org/10.1115/1.4047494
Radiation Science
Radionuclide Composition of Airborne Discharges of European NPPS With WWER, Pressurized Water Reactor, and Boiling Water Reactor Facilities
ASME J of Nuclear Rad Sci. January 2021, 7(1): 012001.
doi: https://doi.org/10.1115/1.4047044
Estimation of Radiological Consequences at a Proposed Nuclear Power Plant Site Using Atmospheric Dispersion Code
ASME J of Nuclear Rad Sci. January 2021, 7(1): 012002.
doi: https://doi.org/10.1115/1.4048026
Topics:
Accidents
,
Meteorology
,
Nuclear power stations
,
Radioisotopes
,
Stability
,
Coolants
,
Radiation (Physics)
,
Plumes (Fluid dynamics)
,
Water
,
Evacuations
Fusion Engineering
Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks
ASME J of Nuclear Rad Sci. January 2021, 7(1): 012301.
doi: https://doi.org/10.1115/1.4048007
Topics:
Accidents
,
Computational fluid dynamics
,
Design
,
Flanges
,
Insulation
,
Pressure
,
Stress
,
Temperature
,
Temperature gradient
,
Thermal analysis
Technical Briefs
A Theory and Model of Molten Salt Reactor Xenon Behavior After the Solubility Limit
ASME J of Nuclear Rad Sci. January 2021, 7(1): 014501.
doi: https://doi.org/10.1115/1.4046909
Topics:
Fuels
,
Molten salt reactors
,
Steady state
,
Bubbles
Assessment of the External and Internal Exposure Risk Index and the Annual Gonadals Equivalent Dose Due to Cement in Côte D'Ivoire
ASME J of Nuclear Rad Sci. January 2021, 7(1): 014502.
doi: https://doi.org/10.1115/1.4046256
Topics:
Cements (Adhesives)
,
Risk
,
Radioisotopes
Benefits, Drawbacks, and Future Trends of Brayton Helium Gas Turbine Cycles for Gas-Cooled Fast Reactor and Very-High Temperature Reactor Generation IV Nuclear Power Plants
Arnold Gad-Briggs, Emmanuel Osigwe, Pericles Pilidis, Theoklis Nikolaidis, Suresh Sampath, Joao Amaral Teixeira
ASME J of Nuclear Rad Sci. January 2021, 7(1): 014503.
doi: https://doi.org/10.1115/1.4047773
Topics:
Cycles
,
Design
,
Helium
,
Nuclear power stations
,
Temperature
,
Gas turbines
,
Coolants
,
Fast neutron reactors
Email alerts
RSS Feeds
Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
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Introduction to Nuclear Forensics Analysis Techniques
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