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Issues
July 2015
ISSN 2332-8983
EISSN 2332-8975
In this Issue
Research Papers
Investigation of Buoyancy Effects on Heat Transfer Characteristics of Supercritical Carbon Dioxide in Heating Mode
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031001.
doi: https://doi.org/10.1115/1.4029592
Topics:
Buoyancy
,
Flow (Dynamics)
,
Heat flux
,
Heat transfer
,
Supercritical carbon dioxide
,
Temperature
,
Wall temperature
,
Pressure
Noncontact Measurement Method of Vibration Stress Using Optical Displacement Sensors for Piping Systems in Nuclear Power Plants
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031002.
doi: https://doi.org/10.1115/1.4029338
Topics:
Stress
,
Vibration
,
Pipes
,
Sensors
,
Displacement
Thermodynamics of Nuclear Waste Reprocessing: Separation of Lanthanides Using Liquid Metals and Alloys
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031003.
doi: https://doi.org/10.1115/1.4029790
Topics:
Alloys
,
Liquid metals
,
Melting
,
Metals
,
Neodymium
,
Separation (Technology)
,
Thermodynamics
Cross-Section Influence on Monte Carlo-Based Burn-Up Codes Applied to a GFR-Like Configuration
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031004.
doi: https://doi.org/10.1115/1.4029521
Multifragmentation Markov Modeling of a Reactor Trip System
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031005.
doi: https://doi.org/10.1115/1.4029342
Topics:
Computer software
,
Design
,
Failure
,
Modeling
,
Stiffness
,
Control systems
,
Instrumentation
,
Maintenance
,
Numerical analysis
High-Efficiency Gamma-Beta Blind Alpha Spectrometry for Nuclear Energy Applications
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031006.
doi: https://doi.org/10.1115/1.4029926
Topics:
Alpha decay
,
Fluids
,
Isotopes
,
Nuclear fission
,
Pressure
,
Sensors
,
Spectroscopy
,
Tension
,
Neutrons
,
Simulation
A Control-Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead-Cooled Fast Reactor
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031007.
doi: https://doi.org/10.1115/1.4029791
Topics:
Diffusion (Physics)
,
Eigenfunctions
,
Fast neutron reactors
,
Fuels
,
Modeling
,
Simulation
,
Temperature
,
Transients (Dynamics)
,
Neutron flux
,
Neutrons
Assessment of Weld Residual Stress Measurement Precision: Mock-Up Design and Results for the Contour Method
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031008.
doi: https://doi.org/10.1115/1.4029413
Topics:
Stress
,
Welded joints
,
Welding
,
Design
Observations in Changes of Electrical Properties in Thermally Neutron-Exposed Boron-Doped Silicon Semiconductors
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031009.
doi: https://doi.org/10.1115/1.4029961
Technical Brief
Dynamic Flowgraph Methodology Assessment of an FPGA-Based Postaccident Monitoring System for Westinghouse AP1000 Nuclear Power Plants
ASME J of Nuclear Rad Sci. July 2015, 1(3): 034501.
doi: https://doi.org/10.1115/1.4029591
Topics:
Design
,
Design for Manufacturing
,
Instrumentation
,
Monitoring systems
,
Nuclear power stations
,
Reliability
,
Calibration
,
Probability
,
Sensors
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Estimation of Turbulent Mixing Factor and Study of Turbulent Flow Structures in Pressurized Water Reactor Sub Channel by Direct Numerical Simulation
ASME J of Nuclear Rad Sci (April 2025)
Heat Flux Correlations for Condensation From Steam and Air Mixtures on Vertical Flat Plates
ASME J of Nuclear Rad Sci (April 2025)
Radiation Monitoring for Volatilized Zinc Contamination Using Gamma-Ray Imaging and Spectroscopy
ASME J of Nuclear Rad Sci (April 2025)
Operation Optimization Framework for Advanced Reactors Using a Data Driven Digital Twin
ASME J of Nuclear Rad Sci
