Number 1
- Table of Contents
- Authors
- Comments on “Thermodynamical Calculations on the Behavior of Gaseous Iodine Species Following a Hypothetical Severe Light Water Reactor Accident”
- Antimony Telluride Formation Hypothesized from Reactor Coolant System Sample Data
- Geological Disposal of Radioactive Waste In Situ Experiments in Granite
- Quantum Electrodynamics of Strong Fields
- Low Reynolds Number Flow Heat Exchangers
- High Pressure Measurement Techniques
- Nuclear Engineering Data Bases, Standards and Numerical Analysis
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 7-18
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A16197
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 19-29
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A16198
Radiological Safety Analysis of the Hot Fuel Examination Facility/South
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 30-41
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A16199
A Reverse Depletion Method for Pressurized Water Reactor Core Reload Design
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 42-54
Technical Paper | Fuel Cycle | doi.org/10.13182/NT86-A16200
Prospects for the Recovery of Uranium from Seawater
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 55-68
Technical Paper | Fuel Cycle | doi.org/10.13182/NT86-A16201
Low-Temperature Conversion of Uranium Oxides to Uranium Hexafluoride Using Dioxygen Difluoride
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 69-71
Technical Paper | Chemical Processing | doi.org/10.13182/NT86-A16202
A Model for the Release of Radioactive Krypton, Xenon, and Iodine from Defective UO2 Fuel Elements
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 72-83
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A16203
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 84-95
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A16204
Residual Depth Profile in the Evaluation of Granular Adsorbents
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 96-101
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A16205
Deformation and Fracture Characteristics for Irradiated Inconel X-750
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 102-108
Technical Paper | Material | doi.org/10.13182/NT86-A16206
Decontamination of Uranium-Contaminated Mild Steel by Melt Refining
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 109-115
Technical Paper | Material | doi.org/10.13182/NT86-A16207
Analysis of Enrichment Factor of Uranium Enrichment by Redox Chromatography
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 116-123
Technical Paper | Radioisotopes and Isotope Separation | doi.org/10.13182/NT86-A16208
Number 2
- Table of Contents
- Authors
- Preface: Performance of Borosilicate Glass High-Level Waste Forms in Disposal Systems
- Symmetries in Nuclear Structure
- Perturbation Methods in Heat Transfer
- Advances in Two-Phase Flow and Heat Transfer, Vols. 1 and 2
- Before It's Too Late
- The Search for Charm, Beauty, and Truth at High Energies
Mechanisms of Defense Waste Glass Dissolution
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 140-164
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33780
Release of Actinides from Defense Waste Glass Under Simulated Repository Conditions
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 165-178
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33781
Modeling of Waste Form Performance and System Release
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 179-187
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33782
International Collaboration in Nuclear Waste Solidification
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 188-198
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33783
Long-Term Release Rates of Borosilicate Glass Waste Forms
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 199-209
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33784
Analysis of High Convertor Pressure Tube Reactors
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 210-219
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Fission Reactor | doi.org/10.13182/NT86-A33785
Reuse System for Powdered Ion-Exchange Resins
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 220-227
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33786
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 228-235
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33787
Analysis of Graphite-Hydrogen-Methane Kinetics Above 1600 K
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 236-242
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Material | doi.org/10.13182/NT86-A33788
Application of the Vortex Method to Analysis of Coolant Temperature Fluctuation
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 243-251
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Heat Transfer and Fluid Flow | doi.org/10.13182/NT86-A33789
Number 3
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 263-277
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A16070
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 278-285
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A16071
Skyshine Radiation from a Pressurized Water Reactor Containment Dome
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 286-295
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A16072
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 296-305
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A16073
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 306-319
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A16074
Uncertainty and Sensitivity Analysis of a Model for Multicomponent Aerosol Dynamics
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 320-342
Technical Paper | Nuclear Safety | doi.org/10.13182/NT86-A16075
Feasibility of the Once-Through Thorium Fuel Cycle for CANDU Reactors
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 343-349
Technical Paper | Fuel Cycle | doi.org/10.13182/NT86-A16076
Structural Chemistry of Solid Solutions in the UO2-Gd2O3 System
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 350-360
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A16077
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 361-377
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT86-A16078
Effect of Heat Flux on the Concentration Factor in Crevices of Nuclear Steam Generators
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 378-383
Technical Paper | Material | doi.org/10.13182/NT86-A16079
Small Calciner for Drying and Calcination of SYNROC Slurry
Nuclear Technology | Volume 73 | Number 3 | June 1986 | Pages 384-388
Technical Note | Radioactive Waste Management | doi.org/10.13182/NT86-A16080