Home / Publications / Journals / Nuclear Technology / Volume 190 / Number 3
Experiments on the Effects of a Spacer Grid in Air-Water Two-Phase Flow
Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 215-224
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-69
Considerations in the Practical Application of the Multisensor Conductivity Probe for Two-Phase Flow
Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 225-235
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-70
Thermal Evaluation of Alternate Shipping Cask for Irradiated Experiments
Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 236-244
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-62
Thermal Predictions of the AGR-2 Experiment with Variable Gas Gaps
Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 245-253
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-73
Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 254-263
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-86
Experiments in Cap-Bubbly Two-Phase Flows for Two-Group IATE Development
Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 264-273
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-71
Estimation of Shear-Induced Lift Force in Laminar and Turbulent Flows
Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 274-291
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-72
Modification of SCWR Assembly Designs with Coupled MCNP5/SCA Methods to Promote Safer Operation
Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 292-300
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-74
Experimental Investigation of Inverted Annular Film Boiling in a Rod Bundle During Reflood Transient
Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 301-312
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-77
An Advanced One-Dimensional Finite Element Model for Incompressible Thermally Expandable Flow
Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 313-322
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-78
The Modeling of Advanced BWR Fuel Designs with the NRC Fuel Depletion Codes PARCS/PATHS
Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 323-335
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-79
Experimental Studies of Spacer Grid Thermal Hydraulics in the Dispersed Flow Film Boiling Regime
Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 336-344
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-80
Effects of SiC and Graphene Oxide Nanoparticle–Coated Surfaces on Quenching Performance
Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 345-358
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-82
On the Steady Mechanical Response of a Heterogeneous Fuel Plate
Nuclear Technology / Volume 190 / Number 3 / June 2015 / Pages 359-375
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-61