Home / Publications / Journals / Nuclear Technology / Volume 68 / Number 1
Reduction in Reactor Vessel Irradiation Through Fuel Management
Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 7-17
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33562
Reducing the Cobalt Inventory in Light Water Reactors
Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 18-28
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33563
Shielding Factors for Gamma Radiation from Activity Deposited on Structures and Ground Surfaces
Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 29-39
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33564
Postirradiation Behavior of UO2 Fuel II: Fragments at 175 to 275°C in Air
Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 40-47
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33565
Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 48-65
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33566
Incineration of Ion Exchange Resins Using Concentric Burners
Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 66-72
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33567
A Simple Probabilistic Risk Analysis for High-Level Waste Repositories
Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 73-76
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33568
ROSA-III Double-Ended Break Test Series for a Loss-of-Coolant Accident in a Boiling Water Reactor
Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 77-93
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33569
Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 94-101
Technical Paper / Analyse / dx.doi.org/10.13182/NT85-A33570
Development of Nuclear Power Plant Noise Diagnostics into a Process-Measuring Method
Nuclear Technology / Volume 68 / Number 1 / January 1985 / Pages 102-110
Technical Note / Fission Reactor / dx.doi.org/10.13182/NT85-A33571