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Issues
January 2016
ISSN 2332-8983
EISSN 2332-8975
In this Issue
Editorial
Editorial
ASME J of Nuclear Rad Sci. January 2016, 2(1): 010201.
doi: https://doi.org/10.1115/1.4031844
Topics:
China
,
Nuclear engineering
,
Nuclear power
,
Radiation (Physics)
,
Safety
,
Statistics
List of Reviewers for 2014
ASME J of Nuclear Rad Sci. January 2016, 2(1): 010202.
doi: https://doi.org/10.1115/1.4031819
List of Reviewers for 2015
ASME J of Nuclear Rad Sci. January 2016, 2(1): 010203.
doi: https://doi.org/10.1115/1.4031820
Guest Editorial
Special Issue: Seventh International Symposium on Supercritical Water-Cooled Reactors
ASME J of Nuclear Rad Sci. January 2016, 2(1): 010301.
doi: https://doi.org/10.1115/1.4031661
Topics:
Supercritical water reactors
,
Water
,
Design
,
Safety
,
Nuclear power
,
Thermal hydraulics
Research Papers
Screening and Correlating Data on Heat Transfer to Fluids at Supercritical Pressure
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011001.
doi: https://doi.org/10.1115/1.4031378
Topics:
Buoyancy
,
Fluids
,
Heat transfer
,
Pressure
,
Shear stress
European Project “Supercritical Water Reactor–Fuel Qualification Test”: Overview, Results, Lessons Learned, and Future Outlook
Mariana Ruzickova, Ales Vojacek, Thomas Schulenberg, Dirk C. Visser, Radek Novotny, Attila Kiss, Csaba Maraczy, Aki Toivonen
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011002.
doi: https://doi.org/10.1115/1.4031034
Topics:
Design
,
Fuels
,
Manufacturing
,
Safety
,
Supercritical water reactors
,
Water
,
Coolants
,
Cladding systems (Building)
,
Pressure
,
Fuel rods
Design of an In-Pile SCWR Fuel Qualification Test Loop
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011003.
doi: https://doi.org/10.1115/1.4030872
Topics:
Circuits
,
Coolants
,
Design
,
Fuel rods
,
Fuels
,
Manufacturing
,
Pressure
,
Safety
,
Supercritical water reactors
,
Temperature
Control Rod Withdrawal Analysis of the Supercritical Water Reactor-Fuel Qualification Test Facility in the LVR-15 Research Reactor
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011004.
doi: https://doi.org/10.1115/1.4030933
Topics:
Fuels
,
Nuclear fuels
,
Safety
,
Scram
,
Temperature
,
Water
,
Pressure
,
Steady state
,
Test facilities
,
Fuel rods
Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011005.
doi: https://doi.org/10.1115/1.4030917
Topics:
Accidents
,
Coolants
,
Design
,
Fuels
,
Pressure
,
Safety
,
Temperature
,
Flow (Dynamics)
,
Failure
,
Heat
Assessment of Computational Tools in Support of Heat-Transfer Correlation Development for Fuel Assembly of Canadian Supercritical Water-Cooled Reactor
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011006.
doi: https://doi.org/10.1115/1.4031283
Topics:
Flow (Dynamics)
,
Fuels
,
Heat transfer
,
Manufacturing
,
Supercritical water reactors
,
Temperature
,
Wall temperature
,
Water
,
Pressure
,
Turbulence
Various Design Aspects of the Canadian Supercritical Water-Cooled Reactor Core
Metin Yetisir, Rui Xu, Michel Gaudet, Mohammad Movassat, Holly Hamilton, Mohammedhossein Nimrouzi, John A. Goldak
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011007.
doi: https://doi.org/10.1115/1.4031247
Topics:
Fuels
,
Pressure
,
Supercritical water reactors
,
Temperature
,
Flow (Dynamics)
,
Water
,
Design
,
Coolants
,
Cladding systems (Building)
,
Manufacturing
Temperature Distribution Inside Fresh-Fuel Pins of Pressure-Tube Supercritical-Water-Cooled Reactor
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011008.
doi: https://doi.org/10.1115/1.4031163
Topics:
Fuels
,
Pins (Engineering)
,
Temperature distribution
,
Temperature
,
Water
,
Pressure
Axial Power and Coolant-Temperature Profiles for a Non-Re-Entrant Pressure-Tube Supercritical Water-Cooled Reactor Fuel Channel
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011009.
doi: https://doi.org/10.1115/1.4031200
Topics:
Coolants
,
Fuels
,
Pressure
,
Simulation
,
Supercritical water reactors
,
Temperature
,
Thermal hydraulics
,
Water
,
Density
Experimental Heat Transfer in an Annular Channel and 3-Rod Bundle Cooled With Upward Flow of Supercritical Water
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011010.
doi: https://doi.org/10.1115/1.4031818
Topics:
Flow (Dynamics)
,
Fluids
,
Heat flux
,
Heat transfer
,
Temperature
,
Wall temperature
,
Water
,
Rods
,
Heat
,
Pressure
Computational Fluid Dynamics Prediction of Heat Transfer in Rod Bundles With Water at Supercritical Pressure
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011011.
doi: https://doi.org/10.1115/1.4031201
Topics:
Boundary-value problems
,
Computational fluid dynamics
,
Geometry
,
Heat transfer
,
Pressure
,
Turbulence
,
Wall temperature
,
Water
,
Flow (Dynamics)
,
Temperature
Sensitivity Studies of Shear Stress Transport Turbulence Model Parameters on the Prediction of Seven-Rod Bundle Benchmark Experiments
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011012.
doi: https://doi.org/10.1115/1.4031035
Numerical Study of Fluid–Structure Interaction With Heat Transfer at Supercritical Pressure in a Fuel Rod Assembly
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011013.
doi: https://doi.org/10.1115/1.4031816
Topics:
Deflection
,
Fluid structure interaction
,
Fluids
,
Heat transfer
,
Rods
,
Temperature
,
Temperature profiles
,
Deformation
,
Fuel rods
,
Manufacturing
Fuel Assembly Design for Supercritical Water-Cooled Reactor
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011014.
doi: https://doi.org/10.1115/1.4030797
Topics:
Design
,
Fuels
,
Manufacturing
,
Water
,
Flow (Dynamics)
,
Supercritical water reactors
,
Cladding systems (Building)
,
Fuel rods
Effect of Thermal Pretreatment on the Corrosion of Stainless Steel in Flowing Supercritical Water
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011015.
doi: https://doi.org/10.1115/1.4031125
Topics:
Alloys
,
Corrosion
,
Corrosion resistance
,
Grain boundaries
,
Intermetallic compounds
,
Oxygen
,
Stainless steel
,
Water
,
Flow (Dynamics)
,
Testing
Assessment of Candidate Fuel Cladding Alloys for the Canadian Supercritical Water-Cooled Reactor Concept
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011016.
doi: https://doi.org/10.1115/1.4031502
Topics:
Alloys
,
Cladding systems (Building)
,
Corrosion
,
Fuels
,
Temperature
,
Steam
,
Supercritical water reactors
,
Water
,
Superheating
,
Weight (Mass)
Oxidation Parameters of Oxide Dispersion-Strengthened Steels in Supercritical Water
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011017.
doi: https://doi.org/10.1115/1.4031127
Oxidation Performance Coating for Future Supercritical Power Plants
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011018.
doi: https://doi.org/10.1115/1.4031379
Topics:
Coating processes
,
Coatings
,
Oxidation
,
Slurries
,
Steel
,
Power stations
,
Alloys
,
Nickel
,
Steam
Effect of Oxidation Chemistry of Supercritical Water on Stress Corrosion Cracking of Austenitic Steels
ASME J of Nuclear Rad Sci. January 2016, 2(1): 011019.
doi: https://doi.org/10.1115/1.4031076
Topics:
Chemistry
,
Fracture (Materials)
,
Steel
,
Stress corrosion cracking
,
Water
,
Water chemistry
,
Oxidation
,
Temperature
,
Supercritical water reactors
,
Oxygen
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