Home / Publications / Journals / Nuclear Technology / Volume 68 / Number 3
Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 275-280
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33574
Primary Coolant Feed and Bleed Operating Regions for the Midland Plant
Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 281-292
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33575
Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 293-310
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33576
Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 311-318
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33577
Optimal Thorium-Fueled CANDU Nuclear Reactor Fuel Management
Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 319-335
Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT85-A33578
Uranium Diffusion in H-451 Graphite
Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 336-343
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33579
High-Temperature Gas-Cooled Reactor Fuel Pressure Vessel Performance Models
Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 344-354
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33580
Rod Bundle Burnout Data and Correlation Comparison
Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 355-369
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33581
Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 370-384
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33582
Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 385-394
Technical Paper / Material / dx.doi.org/10.13182/NT85-A33583
Computational Investigation of Fluid and Thermal Mixing of the EPRI/Creare One-Fifth-Scale Facility
Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 395-407
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33584
Evaluation of Countercurrent Gas/Liquid Flow in Parallel Channels with Restricted Ends
Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 408-417
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33585
Postirradiation Behavior of Naturally and Artificially Defected UO2 Fuel Elements at 250°C in Air
Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 418-422
Technical Note / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33586
Thermal Expansion of U.S. and Australian SYNROC B
Nuclear Technology / Volume 68 / Number 3 / March 1985 / Pages 423-426
Technical Note / Material / dx.doi.org/10.13182/NT85-A33587