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Issues
April 2015
ISSN 2332-8983
EISSN 2332-8975
In this Issue
Research Papers
Enhancing Numerical Stability of a Two-Fluid Model by the Use of Interfacial Pressure Terms
ASME J of Nuclear Rad Sci. April 2015, 1(2): 021001.
doi: https://doi.org/10.1115/1.4029415
Topics:
Boiling
,
Flow (Dynamics)
,
Fluids
,
Numerical stability
,
Pressure
,
Subcooling
,
Two-phase flow
,
Simulation
,
Bubbles
A Physically Based, One-Dimensional Two-Fluid Model for Direct Contact Condensation of Steam Jets Submerged in Subcooled Water
ASME J of Nuclear Rad Sci. April 2015, 1(2): 021002.
doi: https://doi.org/10.1115/1.4029417
Topics:
Condensation
,
Drops
,
Flow (Dynamics)
,
Fluids
,
Jets
,
Steam
,
Water
,
Turbulence
,
Subcooling
,
Temperature
Simulation of Supercritical CO2 Flow Through Circular and Annular Orifice
Haomin Yuan, John Edlebeck, Mathew Wolf, Mark Anderson, Michael Corradini, Sanford Klein, Gregory Nellis
ASME J of Nuclear Rad Sci. April 2015, 1(2): 021003.
doi: https://doi.org/10.1115/1.4029337
Experimental Observations on Wake Characteristics of a Rising Bubble in a Vertical Narrow Rectangular Channel
ASME J of Nuclear Rad Sci. April 2015, 1(2): 021004.
doi: https://doi.org/10.1115/1.4029339
Characterization of Incandescent Particles Emitted by a Cut-Off Grinder During Decommissioning Operations for Evaluating Filter Degradation
ASME J of Nuclear Rad Sci. April 2015, 1(2): 021005.
doi: https://doi.org/10.1115/1.4029343
Topics:
Particulate matter
,
Filters
,
Temperature
Power Cycles of Generation III and III+ Nuclear Power Plants
ASME J of Nuclear Rad Sci. April 2015, 1(2): 021006.
doi: https://doi.org/10.1115/1.4029340
Topics:
Cycles
,
Nuclear power stations
,
Steam
,
Thermal efficiency
Analysis of Focusing Effect of Light Metallic Layer in Stratified Molten Pool Under IVR-ERVC Condition
ASME J of Nuclear Rad Sci. April 2015, 1(2): 021007.
doi: https://doi.org/10.1115/1.4029619
Topics:
Computational fluid dynamics
,
Heat flux
,
Heat transfer
,
Metals
,
Temperature
,
Boundary-value problems
,
Heat
Thermal-Hydraulic and Neutronic Analysis of a Reentrant Fuel-Channel Design for Pressure-Channel Supercritical Water-Cooled Reactors
ASME J of Nuclear Rad Sci. April 2015, 1(2): 021008.
doi: https://doi.org/10.1115/1.4026393
Topics:
Design
,
Fuels
,
Pressure
,
Supercritical water reactors
,
Temperature
,
Water
,
Coolants
Technical Brief
Calculations and Measurements of Pressure Vessel Thermal Neutron Fluxes in the VVER-1000 Mock-Up in the LR-0 Research Reactor
ASME J of Nuclear Rad Sci. April 2015, 1(2): 024509.
doi: https://doi.org/10.1115/1.4029284
Topics:
Neutrons
,
Flux (Metallurgy)
,
Neutron flux
Expert Views
Nuclear Energy Needs a Turning Point Soon
ASME J of Nuclear Rad Sci. April 2015, 1(2): 024710.
doi: https://doi.org/10.1115/1.4029361
Topics:
Nuclear power
,
Turning
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Heat Flux Correlations for Condensation from Steam and Air Mixtures on Vertical Flat Plates
ASME J of Nuclear Rad Sci
Radiation Monitoring for Volatilized Zinc Contamination Using Gamma-Ray Imaging and Spectroscopy
ASME J of Nuclear Rad Sci
