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Issues
January 2017
ISSN 2332-8983
EISSN 2332-8975
In this Issue
Editorial
Editorial Greeting to Journal Readers 2017
ASME J of Nuclear Rad Sci. January 2017, 3(1): 010201.
doi: https://doi.org/10.1115/1.4035065
Topics:
Nuclear engineering
,
Radiation (Physics)
,
China
,
Safety
List of Reviewers for 2016
ASME J of Nuclear Rad Sci. January 2017, 3(1): 010202.
doi: https://doi.org/10.1115/1.4035080
Topics:
Nuclear engineering
,
Radiation (Physics)
Review Article
60 Years in Motion: Short History of Nuclear Engineering Division
ASME J of Nuclear Rad Sci. January 2017, 3(1): 010801.
doi: https://doi.org/10.1115/1.4035177
Research Papers
Transfer and Storage of Molten Salt for the Pyroprocessing of Used Nuclear Fuel
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011001.
doi: https://doi.org/10.1115/1.4032999
Topics:
Containers
,
Storage
,
Switches
,
Vacuum pumps
,
Cooling
Development of Safety Analysis Code TACOS and Application to Fuel Qualification Test Loop
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011002.
doi: https://doi.org/10.1115/1.4035046
Topics:
Accidents
,
Coolants
,
Flow (Dynamics)
,
Fuels
,
Heat
,
Pressure
,
Safety
,
Supercritical water reactors
,
Transients (Dynamics)
,
Water
Bypass Flow Resistance in Prismatic Gas-Cooled Nuclear Reactors
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011003.
doi: https://doi.org/10.1115/1.4035047
Topics:
Flow (Dynamics)
,
Friction
,
Turbulence
,
Computational fluid dynamics
,
Laminar flow
,
Ducts
,
Reynolds number
,
Geometry
Metastable Liquid Cavitation Control (With Memory) Apparatus, Methodology, and Results: For Radiation Detection, Reactor Safety, and Other Industrial Applications
Rusi P. Taleyarkhan, Jeffrey A. Webster, Anthony Sansone, Brian C. Archambault, Randall Reames, Colin D. West
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011004.
doi: https://doi.org/10.1115/1.4034975
Topics:
Cavitation
,
Fluids
,
Glass
,
Radiation (Physics)
,
Testing
,
Water
,
Safety
,
Pressure
,
Tension
,
Nuclear engineering
Study on Sensitivity of Control Rod Cell Model in Reflector Region of High-Temperature Engineering Test Reactor
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011005.
doi: https://doi.org/10.1115/1.4033813
Topics:
High temperature
,
Neutron flux
,
Rods
,
Fuels
,
Design
,
Temperature
,
Computational methods
Integrated Chemical Effects Head Loss Experiments Using Multiconstituent Fibrous Debris Beds
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011006.
doi: https://doi.org/10.1115/1.4034569
Topics:
Aluminum
,
Corrosion
,
Epoxy adhesives
,
Epoxy resins
,
Fibers
,
Metals
,
Temperature
,
Chemistry
,
Water
,
Glass reinforced plastics
Monitoring Pump Parameters in Small Modular Reactors Using Electric Motor Signatures
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011007.
doi: https://doi.org/10.1115/1.4034477
Topics:
Engines
,
Flow (Dynamics)
,
Motors
,
Pumps
,
Pressure
,
Small modular reactors
,
Valves
A Methodology to Analyze the Safety of a Coastal Nuclear Power Plant Against Typhoon External Flooding Risks
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011008.
doi: https://doi.org/10.1115/1.4034974
Topics:
Floods
,
Nuclear power stations
,
Seas
,
Shorelines
,
Simulation
,
Storms
,
Surges
,
Waves
,
Tides
,
Water
Influence of Changes in Pressure and Temperature of Supercritical Water on the Susceptibility to Stress Corrosion Cracking of 316L Austenitic Stainless Steel
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011009.
doi: https://doi.org/10.1115/1.4032780
Topics:
Pressure
,
Temperature
,
Water
,
Stainless steel
,
Oxidation
,
Stress corrosion cracking
Computational Fluid Dynamic Simulation of the Moderator Flow in CANDU-6 Nuclear Reactors
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011010.
doi: https://doi.org/10.1115/1.4032874
Topics:
Flow (Dynamics)
,
Nuclear reactors
,
Simulation
,
Computational fluid dynamics
,
Temperature
Comparison of the Reactivity Effects Calculated by DRAGON and Serpent for a PHWR 37-Element Fuel Bundle
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011011.
doi: https://doi.org/10.1115/1.4034571
Topics:
Coolants
,
Density
,
Fuels
,
Heavy water reactors
,
Temperature
Influence of Pleat Deformation on Pressure Drop for a High-Efficiency Particulate Air Filter: A Small-Scale Experimental Approach
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011012.
doi: https://doi.org/10.1115/1.4034711
Topics:
Deformation
,
Filters
,
Filtration
,
Pressure drop
,
Particulate matter
,
Geometry
Burn-Up Dependency of Control Rod Position at Zero-Power Criticality in the High-Temperature Engineering Test Reactor
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011013.
doi: https://doi.org/10.1115/1.4033812
SMR Fuel Cycle Optimization Using LWROpt
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011014.
doi: https://doi.org/10.1115/1.4034573
A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011015.
doi: https://doi.org/10.1115/1.4034478
Topics:
Heat flux
,
Nucleate boiling
,
Pressurized water reactors
,
Rods
,
Safety
,
Scram
,
Spacetime
,
Thermal hydraulics
,
Transients (Dynamics)
,
Temperature profiles
Full-Scope Probabilistic Safety Assessment of Balakovo Unit 1 in Russia
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011016.
doi: https://doi.org/10.1115/1.4033087
Topics:
Damage
,
Fire
,
Floods
,
Fuels
,
Hazards
,
Probabilistic safety assessment
,
Safety
,
Licensing
,
Nuclear power stations
,
Accidents
Analyses of Simple and Intercooled Recuperated Direct Brayton Helium Gas Turbine Cycles for Generation IV Reactor Power Plants
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011017.
doi: https://doi.org/10.1115/1.4033398
Topics:
Compressors
,
Cycles
,
Helium
,
Pressure
,
Sensitivity analysis
,
Temperature
,
Turbines
,
Thermal efficiency
,
Gas turbines
Innovation of Irradiation Equipment at the LVR-15 Nuclear Research Reactor
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011018.
doi: https://doi.org/10.1115/1.4032599
The Effect of Iron Cross-Section in Thermal Region on Neutron Transport in VVER-1000 Mock-Up in LR-0 Reactor
Martin Schulc, Michal Košťál, Davit Harutyunyan, Marie Švadlenková, Vojtěch Rypar, Ján Milčák, Antonín Kolros
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011019.
doi: https://doi.org/10.1115/1.4034568
Topics:
Iron
,
Neutrons
,
Power density
,
Steel
,
Fuels
,
Pins (Engineering)
,
Sensors
Backbone: A Multiphysics Framework for Coupling Nuclear Codes Based on CORBA and MPI
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011020.
doi: https://doi.org/10.1115/1.4034061
Topics:
Control equipment
,
Design
,
Errors
,
Fuels
,
Safety
,
Simulation
,
Computer programming
,
Nuclear fission
,
Computer software
,
Computer programming languages
Analyses of a High Pressure Ratio Intercooled Direct Brayton Helium Gas Turbine Cycle for Generation IV Reactor Power Plants
ASME J of Nuclear Rad Sci. January 2017, 3(1): 011021.
doi: https://doi.org/10.1115/1.4034479
Topics:
Cycles
,
Pressure
,
Temperature
,
Compressors
,
Turbines
,
Helium
Technical Brief
Optimization for Steam Turbine Cold-End System of a Nuclear Power Plant and Sensitivity Analysis
ASME J of Nuclear Rad Sci. January 2017, 3(1): 014501.
doi: https://doi.org/10.1115/1.4035285
Topics:
Condensers (steam plant)
,
Cooling
,
Optimization
,
Sensitivity analysis
,
Steam turbines
,
Design
,
Nuclear power stations
,
Tariffs
,
Cooling towers
,
Pipes
Validation of the Onsite Used Operational Code Against Burnup Measurement
ASME J of Nuclear Rad Sci. January 2017, 3(1): 014502.
doi: https://doi.org/10.1115/1.4034570
Topics:
Fuels
,
Nuclear fission
,
Nuclear fuel cycle
,
Manufacturing
,
Thermography
,
Spent nuclear fuels
Thermal Hydraulic and Safety Assessment of First Wall Helium Cooling System of a Generalized Test Blanket System in ITER Using RELAP/SCDAPSIM/MOD4.0 Code
ASME J of Nuclear Rad Sci. January 2017, 3(1): 014503.
doi: https://doi.org/10.1115/1.4034680
Topics:
Accidents
,
Coolants
,
Flow (Dynamics)
,
Heat
,
Helium
,
Vessels
,
Safety
,
Cooling systems
,
Design
,
Temperature
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