Number 1
Modernizing and Maintaining Instrumentation and Control Systems in Nuclear Power Plants
Nuclear Technology | Volume 141 | Number 1 | January 2003 | Pages 3-9
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3345
Nuclear Technology | Volume 141 | Number 1 | January 2003 | Pages 10-32
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3346
Nuclear Technology | Volume 141 | Number 1 | January 2003 | Pages 33-44
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3347
Development of an Automated Approach to Control System Design
Nuclear Technology | Volume 141 | Number 1 | January 2003 | Pages 45-53
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3348
Nuclear Technology | Volume 141 | Number 1 | January 2003 | Pages 54-62
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3349
Patterns and Intelligent Systems
Nuclear Technology | Volume 141 | Number 1 | January 2003 | Pages 63-68
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3350
Nuclear Technology | Volume 141 | Number 1 | January 2003 | Pages 69-77
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3351
Nuclear Technology | Volume 141 | Number 1 | January 2003 | Pages 78-87
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3352
Experimental and Numerical Investigation of Boron Dilution Transients in Pressurized Water Reactors
Nuclear Technology | Volume 141 | Number 1 | January 2003 | Pages 88-107
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT03-A3353
Number 2
Nuclear Technology | Volume 141 | Number 2 | February 2003 | Pages 109-121
Technical Paper | Reactor Safety | doi.org/10.13182/NT03-3
Multicycle Optimization of Advanced Gas-Cooled Reactor Loading Patterns Using Genetic Algorithms
Nuclear Technology | Volume 141 | Number 2 | February 2003 | Pages 122-141
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT03-A3355
Nuclear Technology | Volume 141 | Number 2 | February 2003 | Pages 142-156
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT03-A3356
Nuclear Technology | Volume 141 | Number 2 | February 2003 | Pages 157-166
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT03-A3357
Nuclear Technology | Volume 141 | Number 2 | February 2003 | Pages 167-176
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT03-A3358
Nuclear Technology | Volume 141 | Number 2 | February 2003 | Pages 177-185
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT03-A3359
Nuclear Technology | Volume 141 | Number 2 | February 2003 | Pages 186-201
Technical Paper | Accelerators | doi.org/10.13182/NT03-A3360
Nuclear Technology | Volume 141 | Number 2 | February 2003 | Pages 202-210
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT03-A3361
The Effect of Pitch, Burnup, and Absorbers on a TRIGA Spent-Fuel Pool Criticality Safety
Nuclear Technology | Volume 141 | Number 2 | February 2003 | Pages 211-219
Technical Note | Radioactive Waste Management and Disposal | doi.org/10.13182/NT03-A3362
Number 3
Nuclear Technology | Volume 141 | Number 3 | March 2003 | Pages 221-232
Technical Paper | Reactor Safety | doi.org/10.13182/NT03-A3363
Theoretical Analysis for Corium Pool with Miscibility Gap
Nuclear Technology | Volume 141 | Number 3 | March 2003 | Pages 233-243
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT03-A3364
Interaction of Failed Fuel Rods Under Air Ingress Conditions
Nuclear Technology | Volume 141 | Number 3 | March 2003 | Pages 244-256
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT03-A3365
Low-Pressure Corium Dispersion Experiments with Simulant Fluids in a Scaled Annular Cavity
Nuclear Technology | Volume 141 | Number 3 | March 2003 | Pages 257-274
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT03-A3366
Wavelet Integrated System to Calculate Radionuclide Release from a Repository in Fractured Media
Nuclear Technology | Volume 141 | Number 3 | March 2003 | Pages 275-300
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT03-A3367
Cold-Crucible Induction Melter Design and Development
Nuclear Technology | Volume 141 | Number 3 | March 2003 | Pages 301-308
Technical Note | Radioactive Waste Management and Disposal | doi.org/10.13182/NT03-A3368