Volume 190
Number 1 | Number 2 | Number 3
Number 1
Parametric Study of Sloshing Effects in the Primary System of an Isolated Lead-Cooled Fast Reactor
Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 1-10
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-8
Reactivity Swing as a Function of Burnup for Uranium-Fueled Fast Reactors
Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 11-27
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-30
Neutron Multiplicity Measurements With 3He Alternative: Straw Neutron Detectors
Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 28-35
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT14-12
Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 36-51
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-50
Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 52-64
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-31
Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 65-71
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT14-38
Uncertainty Quantification of Concrete Utilized in Dry Cask Storage
Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 72-87
Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-155
New Approach for Fatigue Damage Monitoring Based on Actual Operating History of Nuclear Power Plants
Nuclear Technology / Volume 190 / Number 1 / April 2015 / Pages 88-96
Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT13-150
Number 2
Nuclear Technology / Volume 190 / Number 2 / May 2015 / Pages 97-126
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-40
Nuclear Technology / Volume 190 / Number 2 / May 2015 / Pages 127-160
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-41
Nuclear Technology / Volume 190 / Number 2 / May 2015 / Pages 161-173
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT14-81
Nuclear Technology / Volume 190 / Number 2 / May 2015 / Pages 174-182
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-100
Nuclear Technology / Volume 190 / Number 2 / May 2015 / Pages 183-192
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT14-4
Novel Approach to Extracting Transuranic Elements in Molten Salt Electrorefining
Nuclear Technology / Volume 190 / Number 2 / May 2015 / Pages 193-206
Technical Paper / Reprocessing / dx.doi.org/10.13182/NT14-64
Nuclear Technology / Volume 190 / Number 2 / May 2015 / Pages 207-213
Technical Note / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT14-57
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
