Number 1 | Number 2 | Number 3 | Number 4
Total Energy Investment in Nuclear Power Plants
Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 5-11
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24399
On the Matching of Fusion Breeders to Heavy-Water Reactors
Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 12-22
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24400
Fissile-Solution Storage in Pipes Isolated by Concrete or Water
Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 23-34
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT75-A24401
Diffusion Analyses for Systems of Spherical Particles
Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 35-45
Technical Paper / Material / dx.doi.org/10.13182/NT75-A24402
Fatigue-Crack Propagation in a Cast Stainless Steel
Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 46-53
Technical Paper / Material / dx.doi.org/10.13182/NT75-A24403
Benefit/Risk Analysis of Cardiac Pacemakers Powered by Betacel® Promethium-147 Batteries
Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 54-64
Technical Paper / Radioisotope / dx.doi.org/10.13182/NT75-A24404
Computer Design of High-Explosive Experiments to Simulate Subsurface Nuclear Detonations
Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 65-87
Technical Paper / Nuclear Explosive / dx.doi.org/10.13182/NT75-A24405
Radioactivity Trapped in Melt Produced by a Nuclear Explosion
Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 88-100
Technical Paper / Nuclear Explosive / dx.doi.org/10.13182/NT75-A24406
Dynamic Nondestructive Inspection Using Thermal Neutrons
Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 101-106
Technical Paper / Analysis / dx.doi.org/10.13182/NT75-A24407
Time-Resolved Neutron Radiography Using a Fast Pulse Reactor
Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 107-114
Technical Paper / Technique / dx.doi.org/10.13182/NT75-A24408
A Comprehensive Expression for the Doubling Time of Fast Breeder Reactors
Nuclear Technology / Volume 26 / Number 1 / May 1975 / Pages 115-116
Technical Note / Reactor / dx.doi.org/10.13182/NT75-A24409
New Concepts for Controlled Fusion Reactor Blanket Design
Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 125-145
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24413
Noncoherence and Two-Phase Heat Transfer in LMFBR Fuel-Coolant Interaction
Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 146-164
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24414
Fuel Vapor Generation in LMFBR Core Disruptive Accidents
Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 165-171
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT75-A24415
Investigation of Radial Plutonium Redistribution in Mixed Oxide Fuels Irradiated in a Fast Flux
Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 172-182
Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24416
Development of Brazing Filler Metals for Molybdenum
Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 183-191
Technical Paper / Material / dx.doi.org/10.13182/NT75-A24417
Tritium Absorption in Type 304L Stainless Steel
Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 192-200
Technical Paper / Material / dx.doi.org/10.13182/NT75-A24418
The Development of Californium-252 Sealed Sources at the Commissariat a l’Energie Atomique
Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 201-214
Technical Paper / Radioisotope / dx.doi.org/10.13182/NT75-A24419
Effect of Separation Factors on Product Assay of an Ideal Cascade Composed of UF6 Centrifuges
Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 215-223
Technical Paper / Isotopes Separation / dx.doi.org/10.13182/NT75-A24420
Feasibility Study of In Situ Sediment Analysis by X-Ray Fluorescence
Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 224-231
Technical Paper / Analysis / dx.doi.org/10.13182/NT75-A24421
Fabrication of Thin Uranium Dioxide Films for Neutron Flux Measurements
Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 232-236
Technical Note / Instrument / dx.doi.org/10.13182/NT75-A24422
Vapor Pressure Measurements of Oxide Fuel Between 3000 and 5000 K Using Laser Heating
Nuclear Technology / Volume 26 / Number 2 / June 1975 / Pages 237-241
Technical Note / Technique / dx.doi.org/10.13182/NT75-A24423
Simplified Small-Break Blowdown Models
Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 247-253
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24426
Rocky Flats Experience with Borosilicate Glass Rings for Criticality Control
Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 254-264
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT75-A24427
Nominally Reflected Pipe Intersections Containing Fissile Solution
Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 265-277
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT75-A24428
Swelling of Uranium Silicide Fuel During Postirradiation Heating
Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 278-286
Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24429
The Relationship Between Rupture Life and Creep Properties of Cr —1 Mo Steel
Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 287-296
Technical Paper / Material / dx.doi.org/10.13182/NT75-A24430
Effect of Fast Reactor Fluence on Postirradiation Rupture of Type 316 Stainless Steel
Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 297-306
Technical Paper / Material / dx.doi.org/10.13182/NT75-A24431
A Plutonium-238-Fueled Cardiac Pacemaker
Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 307-319
Technical Paper / Radioisotope / dx.doi.org/10.13182/NT75-A24432
Monte Carlo Dosimetry Calculation for Boron Neutron-Capture Therapy in the Treatment of Brain Tumors
Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 320-339
Technical Paper / Radioisotope / dx.doi.org/10.13182/NT75-A24433
Remote Sensing of Plutonium by the Low-Energy Scattered Flux
Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 340-351
Technical Paper / Analysis / dx.doi.org/10.13182/NT75-A24434
Critical Experiments—Benchmarks (Pu-U Systems)
Nuclear Technology / Volume 26 / Number 3 / July 1975 / Pages 352-381
Technical Note / Chemical Processing / dx.doi.org/10.13182/NT75-A24435
Comparative Study of Radioactivity and Afterheat in Several Fusion Reactor Blanket Designs
Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 391-399
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24440
A Fusion Design Study of Nonmobile Blankets with Low Lithium and Tritium Inventories
Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 400-419
Technical Paper / Reactor / dx.doi.org/10.13182/NT75-A24441
Development of High-Performance Uranium-Metal Fuels for Savannah River Reactors
Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 420-429
Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24442
Effect of a Loss of Flow on a Single LMFBR-Type Fuel Pin
Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 430-441
Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24443
Design of Prototype Carbide Subassemblies and an Evaluation of Proof-Testing Plans in the FFTF
Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 442-451
Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24444
Safety Margins for Sodium-Bonded Carbide Fuel
Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 452-459
Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24445
Optimum Pin Diameter for LMFBR Carbide Fuels
Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 460-471
Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24446
Design and Manufacture of Gas Tags for FFTF Fuel and Control Assemblies
Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 472-479
Technical Paper / Fuel / dx.doi.org/10.13182/NT75-A24447
Diffusion of Linearly Distributed Material in an Evaporating Slab
Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 480-485
Technical Paper / Material / dx.doi.org/10.13182/NT75-A24448
The Influence of Fuel Microstructure on In-Pile Densification
Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 486-495
Technical Paper / Material / dx.doi.org/10.13182/NT75-A24449
Panel Discussion: Engineering Problems in Power Reactor Shielding
Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 496-507
Technical Paper / Shielding / dx.doi.org/10.13182/NT75-A24450
Shielding Design and Analysis Methods for Pressurized Water Reactors
Nuclear Technology / Volume 26 / Number 4 / August 1975 / Pages 508-515
Technical Paper / Shielding / dx.doi.org/10.13182/NT75-A24451