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Issues
July 2022
ISSN 2332-8983
EISSN 2332-8975
In this Issue
SPECIAL SECTION: ISSCWR-10
Editorial
Dr. Romney B. Duffey on His 80th Birthday
Igor Pioro, Richard R. Schultz, Dr. Hideki Kamide, Dr. Sama Bilbao y Leon, Dr. Nils Diaz, Alexander V. Bychkov, Dr. Leon Cizelj, Francesco D'Auria, Dr. Yanping Huang, Dr. Yasuo Koizumi, Tomio Okawa, Dr. Robert Walker, Dr. Robert Youngblood, Enrico Zio
ASME J of Nuclear Rad Sci. July 2022, 8(3): 030201.
doi: https://doi.org/10.1115/1.4054329
Topics:
Accidents
,
Design
,
Electricity (Physics)
,
Governments
,
Innovation
,
Japan Society of Mechanical Engineers
,
Nuclear engineering
,
Nuclear power
,
Risk
,
Safety
Special Papers
Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031101.
doi: https://doi.org/10.1115/1.4053049
Topics:
Coolants
,
Fluids
,
Fuel rods
,
Heat transfer
,
Momentum
,
Temperature
,
Water
,
Wall temperature
,
Flow (Dynamics)
,
Testing
Weight Gain and Hydrogen Absorption in Supercritical Water At 500 °C of Chromium-Coated Zirconium-Based Alloys: Transverse Versus Longitudinal Direction
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031102.
doi: https://doi.org/10.1115/1.4052520
Topics:
Alloys
,
Coatings
,
Corrosion
,
Hydrogen
,
Water
,
Weight (Mass)
,
Zirconium
,
Absorption
,
Coating processes
,
Zirconium alloys
Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031103.
doi: https://doi.org/10.1115/1.4052974
Concept of a Small Modular SCWR With Horizontal Fuel Assemblies
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031104.
doi: https://doi.org/10.1115/1.4052191
Topics:
Coolants
,
Design
,
Fuels
,
Heat
,
Supercritical water reactors
,
Water
,
Temperature
,
Light water reactors
,
Cladding systems (Building)
,
Natural convection
Deteriorated Heat Transfer Influence on the Stress–Strain State of Small Modular Reactors SCWR Fuel Bundles
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031105.
doi: https://doi.org/10.1115/1.4052590
Joining of Zirconium Alloys to Nickel Bearing Alloys for In-Core Components
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031106.
doi: https://doi.org/10.1115/1.4054557
Topics:
Alloys
,
Extruding
,
Friction welding
,
Zirconium alloys
,
Stainless steel
,
Bearings
,
Zirconium
,
Friction
,
Nickel
,
Supercritical water reactors
Mechanical and Microstructural Characterization of Inconel 625 Welds After Corrosion at Supercritical Water Conditions
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031107.
doi: https://doi.org/10.1115/1.4054637
Topics:
Corrosion
,
Welding
,
Phase diagrams
,
Water
,
Welded joints
,
Testing
Next Generation/Advanced Reactors
Hydrogen Deflagration Analysis in THAI Experiments Using MELCOR Code
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031201.
doi: https://doi.org/10.1115/1.4048006
Topics:
Explosions
,
Hydrogen
,
Aerosols
,
Thermal hydraulics
,
Pressure
,
Flames
,
Test facilities
Thermal Hydraulics and CFD
Thermophysical Characteristics of Liquid Metal In-Bi-Sn Eutectic (Field's Metal) as a Similarity Coolant
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031301.
doi: https://doi.org/10.1115/1.4053632
Topics:
Density
,
Liquid metals
,
Metals
,
Temperature
,
Thermal conductivity
,
Viscosity
,
Specific heat
,
Alloys
Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031302.
doi: https://doi.org/10.1115/1.4052808
Topics:
Fuels
,
Heat
,
Nuclear power stations
,
Plastics
,
Pyrolysis
,
Small modular reactors
,
Heating
,
Syngas
,
Temperature
,
Biochar
Reactor Physics
Experimental Investigation of Melt Coolability Behavior in an Ex-Vessel Core Catcher: The Effect of Flooding Time
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031401.
doi: https://doi.org/10.1115/1.4053220
Topics:
Floods
,
Temperature
,
Vessels
,
Water
Development of a Phase-Field Method for Phase Change Simulations Using a Conservative Allen–Cahn Equation
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031402.
doi: https://doi.org/10.1115/1.4052807
Topics:
Boundary-value problems
,
Simulation
,
Wetting
,
Vapors
,
Bubbles
,
Simulation results
Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403.
doi: https://doi.org/10.1115/1.4052014
Topics:
Accidents
,
Boiling water reactors
,
Containment
,
Design
,
Pressure
,
Safety
,
Steam
,
Water
,
Heat
,
Economics
Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031404.
doi: https://doi.org/10.1115/1.4053051
Thermal Stratification in a Pool With Submerged Heater Under Low Frequency Excitation
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031405.
doi: https://doi.org/10.1115/1.4053221
Topics:
Excitation
,
Thermal stratification
,
Water
,
Temperature gradient
,
Temperature
,
Heat
Nuclear Fuels/Cycles and Materials
Physics Modeling for Conceptual Designs of Proposed Experiments in the Zero Energy Deuterium-2 Critical Facility for Testing Small Modular Reactor-Type Fuels
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031501.
doi: https://doi.org/10.1115/1.4054079
Topics:
Fuels
,
Modeling
,
Physics
,
Pressurized water reactors
,
Water
,
Neutrons
,
High temperature
Review of Methods and Results for Reactor Physics Analysis of Thorium-Based Fuels From Irradiation Experiments Conducted in the National Research Universal Reactor
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031502.
doi: https://doi.org/10.1115/1.4053691
Topics:
Fuels
,
Physics
,
Irradiation (Radiation exposure)
Nuclear Safety/Security and Beyond Design Basis Events
Steady-State Subchannel Thermalhydraulic Assessment of a Full-Scale Pressurized Water Reactor-Small Modular Reactor Fuel Assembly With Conventional and Advanced Fuels
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031601.
doi: https://doi.org/10.1115/1.4053829
Topics:
Fuels
,
Manufacturing
,
Temperature
,
Water
Plant Systems, O&M, and Life Cycle
Assessment of Spray and Pool Scrubbing Efficiencies for Means of Mitigation Against Aerosol Dispersion in the Context of Fuel Debris Retrieval at Fukushima Daiichi: Part I
Emmanuel Porcheron, Yohan Leblois, Thomas Gelain, Christophe Chagnot, Christophe Journeau, Damien Roulet
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031701.
doi: https://doi.org/10.1115/1.4051611
Topics:
Aerosols
,
Sprays
,
Particulate matter
,
Laser cutting
,
Fuels
,
Water
,
Drops
Assessment of Spray and Pool Scrubbing Efficiencies for Means of Mitigation Against Aerosol Dispersion in the Context of Fuel Debris Retrieval at Fukushima Daiichi: Part II
Emmanuel Porcheron, Yohan Leblois, Thomas Gelain, Christophe Chagnot, Christophe Journeau, Damien Roulet
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031702.
doi: https://doi.org/10.1115/1.4051538
Topics:
Aerosols
,
Particulate matter
,
Sprays
,
Laser cutting
,
Drops
,
Fuels
,
Water
,
Computer simulation
,
Fukushima nuclear disaster, Japan, 2011
Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031703.
doi: https://doi.org/10.1115/1.4053050
Topics:
Accidents
,
Hydrogen
,
Sensitivity analysis
,
Uncertainty
,
Uncertainty quantification
,
Uncertainty analysis
,
Design
,
Optimization
RAW Management and Decommissioning
Thermal Fatigue of Pressurized Water Reactor Coolant System Loop Drain Lines Due to Outflow Activities
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031801.
doi: https://doi.org/10.1115/1.4053013
Topics:
Chemistry
,
Coolants
,
Fatigue
,
Flow (Dynamics)
,
Outflow
,
Pipes
,
Pressurized water reactors
,
Stress
,
Temperature
,
Thermal stratification
High Reliability Microgrid for a Nuclear Facility Emergency Power Supply
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031802.
doi: https://doi.org/10.1115/1.4046353
Topics:
Microgrids
,
Reliability
,
Batteries
,
Diesel generators
,
Failure
,
Risk-based design
,
Emergency power
,
Probability
,
Nuclear power stations
Radiation Science
Safety of Radioactive Materials Transportation and Storing Assisted by Internet of Things
ASME J of Nuclear Rad Sci. July 2022, 8(3): 031901.
doi: https://doi.org/10.1115/1.4048113
Topics:
Heat
,
Radioactive substances
,
Safety
,
Security
,
Transportation systems
,
Internet of things
,
Embedded systems
,
Sensors
,
Vehicles
,
Radiation (Physics)
Code and Regulatory Issues
Radiation-Induced Surface Wettability Enhancement of an Indium Tin Oxide and Titanium Oxide Film-Coated Sapphire
ASME J of Nuclear Rad Sci. July 2022, 8(3): 032001.
doi: https://doi.org/10.1115/1.4051791
Radon Equilibrium Equivalent Concentration Uncertainty of Calibration System With Alpha Self-Absorption Consideration
ASME J of Nuclear Rad Sci. July 2022, 8(3): 032002.
doi: https://doi.org/10.1115/1.4048633
Topics:
Equilibrium (Physics)
,
Uncertainty
,
Calibration
,
Absorption
,
Filters
,
Radiation measurement
,
Sensors
Estimating Radon Excess Lung Cancer at the Babylon Cement Plant in Iraq
ASME J of Nuclear Rad Sci. July 2022, 8(3): 032003.
doi: https://doi.org/10.1115/1.4049757
Pane Discussion
Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER
ASME J of Nuclear Rad Sci. July 2022, 8(3): 032301.
doi: https://doi.org/10.1115/1.4053828
Technical Briefs
Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance
ASME J of Nuclear Rad Sci. July 2022, 8(3): 034501.
doi: https://doi.org/10.1115/1.4053689
Topics:
Filters
,
Pipes
,
Signals
,
Stress
,
Temperature
,
Monitoring systems
,
Nuclear power stations
Theoretical Approach for the Fast Estimation of the Turbulent Kinematic Viscosity for Internal Flows
ASME J of Nuclear Rad Sci. July 2022, 8(3): 034502.
doi: https://doi.org/10.1115/1.4054342
Topics:
Flow (Dynamics)
,
Internal flow
,
Kinematics
,
Turbulence
,
Viscosity
,
Simulation
,
Eddies (Fluid dynamics)
Efficient Neutron Irradiation Procedure for Uniform Dopant Distributions in Silicon Doping
ASME J of Nuclear Rad Sci. July 2022, 8(3): 034503.
doi: https://doi.org/10.1115/1.4054005
Topics:
Irradiation (Radiation exposure)
,
Neutron flux
,
Neutrons
,
Silicon
Discussion
Suggestion on Improving Small Branch BOSS Joints Welding Quality
ASME J of Nuclear Rad Sci. July 2022, 8(3): 035501.
doi: https://doi.org/10.1115/1.4053690
Topics:
Design
,
Nondestructive evaluation
,
Welding
Email alerts
RSS Feeds
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