Number 1 | Number 2 | Number 3
Summary of the ALARA Nature of Design Effluents from the Clinch River Breeder Reactor Plant
Nuclear Technology / Volume 42 / Number 1 / January 1979 / Pages 5-12
Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32157
Assessment of Criticality Safety
Nuclear Technology / Volume 42 / Number 1 / January 1979 / Pages 13-21
Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32158
A Parametric Study of a Lithium-Cooled Tokamak Blanket
Nuclear Technology / Volume 42 / Number 1 / January 1979 / Pages 22-33
Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32159
Nuclear Technology / Volume 42 / Number 1 / January 1979 / Pages 34-50
Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32160
Decision Table Development and Application to the Construction of Fault Trees
Nuclear Technology / Volume 42 / Number 1 / January 1979 / Pages 51-64
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT79-A32161
Proposed Extension of Raschig Ring Standard to Low Enriched Uranium Fuels
Nuclear Technology / Volume 42 / Number 1 / January 1979 / Pages 65-70
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT79-A32162
Proton Simulation of Irradiation-Induced Creep
Nuclear Technology / Volume 42 / Number 1 / January 1979 / Pages 71-81
Technical Paper / Material / dx.doi.org/10.13182/NT79-A32163
Low Cycle Fatigue Behavior of Types 304 and 316 Stainless Steel Tested in Sodium at 550°C
Nuclear Technology / Volume 42 / Number 1 / January 1979 / Pages 82-89
Technical Paper / Material / dx.doi.org/10.13182/NT79-A32164
Garden Hose Separation of Gaseous Isotopes. Part II: Supersonic Accelerations
Nuclear Technology / Volume 42 / Number 1 / January 1979 / Pages 90-101
Technical Paper / Isotopes Separation / dx.doi.org/10.13182/NT79-A32165
Nuclear Technology / Volume 42 / Number 1 / January 1979 / Pages 102-111
Technical Paper / Analysis / dx.doi.org/10.13182/NT79-A32166
Nuclear Technology / Volume 42 / Number 2 / February 1979 / Pages 119-122
Department / Thorium Fuel Cycle in a Breeder Economy / dx.doi.org/10.13182/NT79-A32141
Reactor Physics Parameters of Alternate Fueled Fast Breeder Reactor Core Designs
Nuclear Technology / Volume 42 / Number 2 / February 1979 / Pages 123-132
Technical Paper / Thorium Fuel Cycle in a Breeder Economy / Fuel Cycle / dx.doi.org/10.13182/NT79-A32142
Performance of Thorium-Fueled Fast Breeders
Nuclear Technology / Volume 42 / Number 2 / February 1979 / Pages 133-143
Technical Paper / Thorium Fuel Cycle in a Breeder Economy / Fuel Cycle / dx.doi.org/10.13182/NT79-A32143
The Denatured Thorium Cycle—An Overview
Nuclear Technology / Volume 42 / Number 2 / February 1979 / Pages 144-149
Technical Paper / Thorium Fuel Cycle in a Breeder Economy / Reactor / dx.doi.org/10.13182/NT79-A32144
Pulsed Reactivity Measurements of Large 235U-AI Castings in H2O
Nuclear Technology / Volume 42 / Number 2 / February 1979 / Pages 150-154
Technical Paper / Thorium Fuel Cycle in a Breeder Economy / Reactor / dx.doi.org/10.13182/NT79-A32145
Rock Cavity Construction of a Nuclear Power Plant—A Case Study
Nuclear Technology / Volume 42 / Number 2 / February 1979 / Pages 155-162
Technical Paper / Thorium Fuel Cycle in a Breeder Economy / Reactor Siting / dx.doi.org/10.13182/NT79-A32146
Preparation of Uranium Kernels by an External Gelation Process
Nuclear Technology / Volume 42 / Number 2 / February 1979 / Pages 163-171
Technical Paper / Thorium Fuel Cycle in a Breeder Economy / Chemical Processing / dx.doi.org/10.13182/NT79-A32147
Nuclear Technology / Volume 42 / Number 2 / February 1979 / Pages 172-179
Technical Paper / Thorium Fuel Cycle in a Breeder Economy / Chemical Processing / dx.doi.org/10.13182/NT79-A32148
A Neutronic Assessment of Strontium-90 Transmutation in Fusion Reactors
Nuclear Technology / Volume 42 / Number 2 / February 1979 / Pages 180-194
Technical Paper / Thorium Fuel Cycle in a Breeder Economy / Radioactive Waste / dx.doi.org/10.13182/NT79-A32149
The Effects of Stoichiometry on Cladding Attack in UO2-PuO2
Nuclear Technology / Volume 42 / Number 2 / February 1979 / Pages 195-206
Technical Paper / Thorium Fuel Cycle in a Breeder Economy / Material / dx.doi.org/10.13182/NT79-A32150
Nuclear Technology / Volume 42 / Number 2 / February 1979 / Pages 207-215
Technical Paper / Thorium Fuel Cycle in a Breeder Economy / Material / dx.doi.org/10.13182/NT79-A32151
Experimental Parameter Investigations on the Tribological Behavior of Stellite 6 in Liquid Sodium
Nuclear Technology / Volume 42 / Number 2 / February 1979 / Pages 216-223
Technical Paper / Thorium Fuel Cycle in a Breeder Economy / Material / dx.doi.org/10.13182/NT79-A32152
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 237-249
Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32178
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 250-263
Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32179
Characterization of Fragmented Fuel from a Thermal Fuel-Sodium Interaction
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 264-271
Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32180
Hydrogen Transport in a Toroidal Plasma Using Multigroup Discrete-Ordinates Methodology
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 272-288
Technical Paper / Reactor / dx.doi.org/10.13182/NT79-A32181
Loss-of-Coolant Accidents in Small Compact Nuclear Reactors
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 289-296
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT79-A32182
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 297-303
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT79-A32183
Some Calculations of the Failure Statistics of Coated Fuel Particles
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 304-311
Technical Paper / Fuel / dx.doi.org/10.13182/NT79-A32184
Tritium Permeation Through Fe-2¼Cr-1 Mo Steam Generator Material
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 312-319
Technical Paper / Material / dx.doi.org/10.13182/NT79-A32185
Filtration of Sodium-Fire Aerosols
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 320-323
Technical Paper / Material / dx.doi.org/10.13182/NT79-A32186
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 324-331
Technical Paper / Material / dx.doi.org/10.13182/NT79-A32187
Calculation of the Influence of the Radial Temperature Gradient on Cladding Dilatation
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 332-334
Technical Paper / Material / dx.doi.org/10.13182/NT79-A32188
Arguments Concerning the Evaluation of Cladding Dilatation due to Thermodiffusion
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Page 335
Department / Letter to the Editor / dx.doi.org/10.13182/NT79-A32189
The Mass Spectrometric Determination of Uranium-235 in Uranium Hexafluoride
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 337-342
Technical Paper / Analysis / dx.doi.org/10.13182/NT79-A32190
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 343-349
Technical Paper / Technique / dx.doi.org/10.13182/NT79-A32191
Bubble Worth Variation in Molten Cores from a Hypothetical Core Disruptive Acident
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 350-352
Technical Note / Reactor / dx.doi.org/10.13182/NT79-A32192
Nuclear Technology / Volume 42 / Number 3 / March 1979 / Pages 353-361
Technical Note / Fuel Cycle / dx.doi.org/10.13182/NT79-A32193