Number 1
Radioactive Fission Product Release from Defective Light Water Reactor Fuel Elements
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 1-16
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3273
Thorium Fuel Performance in a Tight-Pitch Light Water Reactor Lattice
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 17-29
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3274
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 30-43
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3275
Modeling of Hydrogen Flame Propagation in Multicompartment Buildings
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 44-57
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3276
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 58-68
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3277
The Effect of Hydrogen on Oxidative Dissolution of Spent Fuel
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 69-78
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT02-A3278
Analysis of External Cooling of the Reactor Vessel During Severe Accidents
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 79-89
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT02-A3279
An Estimate of the Crust Thickness on the Surface of a Thermally Convecting Liquid-Metal Pool
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 90-92
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT02-A3280
Cost of Electricity from Molten Salt Reactors
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 93-95
Technical Note | Economics of Nuclear Systems | doi.org/10.13182/NT02-A3281
Number 2
Revised Burnup Code System SWAT: Description and Validation Using Postirradiation Examination Data
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 97-110
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3282
Assessment of Homogeneous Thorium/Uranium Fuel for Pressurized Water Reactors
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 111-122
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT01-21
Advantages of Irradiated DUPIC Fuels from the Perspective of Environmental Impact
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 123-139
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3284
Lateral Mixing Mechanisms in Vertical and Horizontal Interconnected Subchannel Two-Phase Flows
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 140-161
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT138-140
Chemical Speciation of Iodine Source Term to Containment
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 162-178
Technical Paper | Reactor Safety | doi.org/10.13182/NT138-162
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 179-205
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3287
Pyrolysis Kinetics of Spent Low-Level Radioactive Resin
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 206-210
Technical Note | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3288
A Comparison of Direct Gamma Dose Rates from a Stationary Gaussian Plume Using Different Models
Nuclear Technology | Volume 138 | Number 2 | May 2002 | Pages 211-216
Technical Note | Environmental Science, Technology and Effects | doi.org/10.13182/NT02-A3289
Number 3
Spatial Control of a Large PHWR via Reduced Model
Nuclear Technology | Volume 138 | Number 3 | June 2002 | Pages 217-237
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT02-A3290
ODS Steel Clad MOX Fuel-Pin Fabrication and Irradiation Performance in EBR-II
Nuclear Technology | Volume 138 | Number 3 | June 2002 | Pages 238-245
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3291
High-Burnup BWR Fuel Behavior Under Simulated Reactivity-Initiated Accident Conditions
Nuclear Technology | Volume 138 | Number 3 | June 2002 | Pages 246-259
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3292
A Fission Gas Release Model for High-Burnup LWR ThO2-UO2 Fuel
Nuclear Technology | Volume 138 | Number 3 | June 2002 | Pages 260-272
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT02-A3293
Nuclear Technology | Volume 138 | Number 3 | June 2002 | Pages 273-283
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT02-A3294
Transmutation in the Nuclear Fuel Cycle: Approaches and Impacts
Nuclear Technology | Volume 138 | Number 3 | June 2002 | Pages 284-299
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT02-A3295
Nuclear Technology | Volume 138 | Number 3 | June 2002 | Pages 300-312
Technical Paper | Accelerators | doi.org/10.13182/NT02-1