Number 1 | Number 2 | Number 3
Thermal-Hydraulic Design of the Accelerator Production of Tritium Tungsten Neutron Source
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 3-14
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3125
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 15-29
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3126
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 30-48
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3127
Target Systems Overview for the Spallation Neutron Source
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 49-60
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3128
Intensity and Spectra of a White Light Neutron Source Produced by a 70-MeV Proton Accelerator
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 61-65
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3129
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 66-93
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-1
Neutronic Design Studies for the Spallation Neutron Source
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 94-102
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3131
The Accelerator Production of Tritium Materials Test Program
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 103-114
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3132
Target/Blanket Design for the Accelerator Production of Tritium Plant
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 115-127
Technical Paper / Accelerator Applications / dx.doi.org/10.13182/NT00-A3133
Benchmark Calculations for Standard and DUPIC CANDU Fuel Lattices Compared with the MCNP-4B Code
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 128-151
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT00-A3134
Mitigation Measures Following a Loss-of-Residual-Heat-Removal Event During Shutdown
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 152-166
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3135
Nuclear Technology / Volume 132 / Number 1 / October 2000 / Pages 167-178
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3136
Nuclear Technology / Volume 132 / Number 2 / November 2000 / Pages 179-195
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT00-A3137
Analysis of Kuosheng Station Blackout Accident Using MELCOR 1.8.4
Nuclear Technology / Volume 132 / Number 2 / November 2000 / Pages 196-205
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT00-A3138
Comparison of CECOR Algorithm to Lagrange Multiplier Method to Estimate Reactor Power Distributions
Nuclear Technology / Volume 132 / Number 2 / November 2000 / Pages 206-213
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT00-A3139
Nuclear Technology / Volume 132 / Number 2 / November 2000 / Pages 214-226
Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT00-A3140
Nuclear Technology / Volume 132 / Number 2 / November 2000 / Pages 227-239
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3141
Constant-Temperature Calorimetry for In-Core Power Measurement
Nuclear Technology / Volume 132 / Number 2 / November 2000 / Pages 240-255
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3142
Nuclear Technology / Volume 132 / Number 2 / November 2000 / Pages 256-280
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3143
Analyses and Development of Effective Compensation Shields in a Multilegged Duct Streaming System
Nuclear Technology / Volume 132 / Number 2 / November 2000 / Pages 281-289
Technical Paper / Radiation Protection / dx.doi.org/10.13182/NT00-A3144
Nuclear Technology / Volume 132 / Number 2 / November 2000 / Pages 290-308
Technical Paper / Decontamination/Decommissioning / dx.doi.org/10.13182/NT00-A3145
Nuclear Technology / Volume 132 / Number 2 / November 2000 / Pages 309-324
Technical Paper / Radioisotopes / dx.doi.org/10.13182/NT00-A3146
TRIGA Mark II Criticality Benchmark Experiment with Burned Fuel
Nuclear Technology / Volume 132 / Number 3 / December 2000 / Pages 325-338
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT00-A3147
A Model for Calculating the Accident Washout Factor for a Coastal Nuclear Power Plant Site
Nuclear Technology / Volume 132 / Number 3 / December 2000 / Pages 339-351
Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT00-A3148
Optimization of the Surveillance Test Interval of the Safety Systems at the Plant Level
Nuclear Technology / Volume 132 / Number 3 / December 2000 / Pages 352-365
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT00-A3149
Nuclear Technology / Volume 132 / Number 3 / December 2000 / Pages 366-374
Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT00-A3150
Direct-Contact Heat Transfer Model for Dispersed-Flow Film Boiling
Nuclear Technology / Volume 132 / Number 3 / December 2000 / Pages 375-388
Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT00-A3151
Neurocontrol of Pressurized Water Reactors in Load-Follow Operations
Nuclear Technology / Volume 132 / Number 3 / December 2000 / Pages 389-402
Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT00-4
Nuclear Technology / Volume 132 / Number 3 / December 2000 / Pages 403-412
Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT00-A3153
Nuclear Technology / Volume 132 / Number 3 / December 2000 / Pages 413-423
Technical Paper / Reprocessing / dx.doi.org/10.13182/NT00-A3154
Efficient Simulation Modeling of an Integrated High-Level-Waste Processing Complex
Nuclear Technology / Volume 132 / Number 3 / December 2000 / Pages 424-435
Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT00-A3155