Number 1 | Number 2 | Number 3
Gaussian Processes for State Identification in Pressurized Water Reactors
Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 1-12
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT13-A15821
Assessment of the Efficiency of Extended Power Uprates at U.S. Boiling Water Reactors
Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 13-25
Technical Paper / Fission Reactors/Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT13-A15822
Salt-Cooled Modular Innovative Thorium Heavy Water-Moderated Reactor System
Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 26-38
Technical Paper / Fission Reactors/Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A15823
Viability Assessment of Noble Gas Bundle Tagging for Failed-Fuel Identification in CANDU Reactors
Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 39-48
Technical Paper / Fission Reactors/Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A15824
The Effect of Coating Parameters and Annealing on the Crushing Strength of TRISO Coated Particles
Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 49-56
Technical Paper / Fission Reactors/Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A15825
The Role of Gd2O3 Phase Transition on UO2-Gd2O3 Fuel Sintering
Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 57-62
Technical Paper / Fuel Cycle and Management/Miscellaneous / dx.doi.org/10.13182/NT13-A15826
Hybrid Monte Carlo/Deterministic Methods for Accelerating Active Interrogation Modeling
Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 63-74
Technical Paper / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-A15827
Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 75-83
Technical Paper / Nuclear Plant Operations and Control/Miscellaneous / dx.doi.org/10.13182/NT13-A15828
Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 84-97
Technical Paper / Reprocessing / dx.doi.org/10.13182/NT13-A15829
Modeling the Anodic Behavior of U, Zr, and U-Zr Alloy in Molten LiCl-KCl Eutectic
Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 98-110
Technical Paper / Reprocessing / dx.doi.org/10.13182/NT182-98
Long-Term Electrochemical Criteria for Crevice Corrosion in Concentrated Chloride Solutions
Nuclear Technology / Volume 182 / Number 1 / April 2013 / Pages 111-122
Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT13-A15831
Simulation of Pellet-Cladding Interaction with the PLEIADES Fuel Performance Software Environment
Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 124-137
Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A16424
On the Response of Ionic Crystals to Irradiation
Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 138-144
Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A16425
Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 145-154
Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A16426
Microstructurally Explicit Simulation of Intergranular Mass Transport in Oxide Nuclear Fuels
Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 155-163
Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A16427
Transmission Electron Microscopy Investigation of Krypton Bubbles in Polycrystalline CeO2
Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 164-169
Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Materials for Nuclear Systems / dx.doi.org/10.13182/NT13-A16428
Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 170-186
Regular Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fission Reactors / dx.doi.org/10.13182/NT13-A16429
Introduction of Thorium-Based Fuels in High Conversion Pressurized Water Reactors
Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 187-206
Regular Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fission Reactors / dx.doi.org/10.13182/NT13-A16430
Determining Optimal Neutron Spectra for Transmutation and Isotope Management
Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 207-223
Regular Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Fission Reactors / dx.doi.org/10.13182/NT13-A16431
Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 224-234
Regular Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Radiation Transport and Protection / dx.doi.org/10.13182/NT13-A16432
Study on UF-2 Extraction in Accelerator Mass Spectrometry Measurement of 236U
Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 235-241
Regular Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Reprocessing / dx.doi.org/10.13182/NT13-A16433
Laser-Assisted Decontamination of Fuel Pins for Prototype Fast Breeder Reactor
Nuclear Technology / Volume 182 / Number 2 / May 2013 / Pages 242-247
Regular Technical Paper / Special Issue on the Symposium on Radiation Effects in Ceramic Oxide and Novel LWR Fuels / Decontamination/Decommissioning / dx.doi.org/10.13182/NT13-A16434
Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 249-258
Technical Paper / Fission Reactors/Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT13-A16977
Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 259-273
Technical Paper / Fuel Cycle and Management/Thermal Hydraulics / dx.doi.org/10.13182/NT12-58
Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 274-285
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A16979
A Study of Nanoparticle Surface Modification Effects on Pool Boiling Critical Heat Flux
Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 286-301
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A16980
The Triggerability and Explosion Potentials of Reactor Core Melt at Fuel Coolant Interactions
Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 302-314
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT13-A16981
Thermal-Hydraulic Analysis for HEU and LEU Transitional Core Conversion of the MIT Research Reactor
Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 315-334
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT12-81
Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 335-348
Technical Paper / Radiation Transport and Protection/Radioisotopes / dx.doi.org/10.13182/NT13-A16983
Application of Zirconium Alloys for Reprocessing Plant Components
Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 349-357
Technical Paper / Reprocessing/Materials for Nuclear Systems / dx.doi.org/10.13182/NT12-73
Intelligent Radioactive Waste Management Platform for Radioactive Waste Storage Facilities
Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 358-368
Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT13-A16985
Nuclear Technology / Volume 182 / Number 3 / June 2013 / Pages 369-377
Technical Note / Fuel Cycle and Management / dx.doi.org/10.13182/NT13-A16986