Volume 154
Number 1 | Number 2 | Number 3
Number 1
Investigations of Hydraulic Behavior in Spallation Target Configurations
Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 1-12
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3714
Internal Vessel Cooling Feasibility Attributed by Critical Heat Flux in Inclined Rectangular Gap
Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 13-40
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3715
Neutronic and Safety Aspects of a Gas-Cooled Subcritical Core for Minor Actinide Transmutation
Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 41-51
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3716
Subchannel Analysis of Fuel Assemblies of European Experimental ADS
Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 52-68
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3717
Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 69-84
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3718
Aerosol Retention Near the Tube Breach During Steam Generator Tube Rupture Sequences
Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 85-94
Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT06-A3719
Separations and Transmutation Criteria to Improve Utilization of a Geologic Repository
Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 95-106
Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-3
Results of the QUENCH-09 Experiment Compared to QUENCH-07 with Incorporation of B4C Absorber
Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 107-116
Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT06-A3721
Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 117-127
Technical Paper / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT06-A3722
Number 2
Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 129-141
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-1
Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 142-154
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3724
Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 155-169
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT06-A3725
Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 170-185
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT06-A3726
Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 186-193
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3727
Modeling of Radiative Heat Transfer During a PWR Severe Accident
Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 194-214
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3728
The Core Characteristics of a LOCA Power Pulse in a CANDU-6 Reactor with the CANFLEX-RU Fuel
Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 215-223
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT06-A3729
Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 224-236
Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT06-A3730
Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 237-246
Technical Paper / Reprocessing / dx.doi.org/10.13182/NT06-A3731
Thermal-Hydrologic Model Study for an Alternative Waste Package Design for Yucca Mountain Repository
Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 247-264
Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3732
Number 3
High-Performance Supercritical Carbon Dioxide Cycle for Next-Generation Nuclear Reactors
Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 265-282
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT154-265
The Supercritical Carbon Dioxide Power Cycle: Comparison to Other Advanced Power Cycles
Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 283-301
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3734
Behavior of VVER Fuel Rods Tested Under Severe Accident Conditions in the CODEX Facility
Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 302-317
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT06-A3735
Reduction in Workload of BWR In-Core Fuel Shuffling by New Optimization Methods
Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 318-327
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3736
Analysis of the Bubbly-Churn Regime Transition in a Scaled Model Boiling Water Reactor
Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 328-334
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3737
Heat Transfer in a Supercritical Fluid: Classification of Heat Transfer Regimes
Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 335-349
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3738
Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 350-360
Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT06-A3739
Proliferation-Resistant SIGMA Uranium Enrichment Plants
Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 361-373
Technical Paper / Enrichment / dx.doi.org/10.13182/NT06-A3740
Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 374-388
Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3741
