Number 1 | Number 2 | Number 3 | Number 4
Modeling of Thermionic Reactor Systems for Dynamics Studies
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 7-18
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30897
Pulsed-Neutron and Exponential Experiments with Mixed-Fuel Lattices
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 19-28
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30898
A Vibrating Bar Technique for Preparing Carbon Microspheres
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 29-37
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT71-A30899
Application of Fuel-Element Modeling Codes to EBR-II Driver Fuel
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 38-44
Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A30900
Influence of Irradiation Temperature on the Creep-Rupture Properties of Hastelloy-N
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 45-60
Technical Paper / Material / dx.doi.org/10.13182/NT71-A30901
Techniques in Monte Carlo Analysis Applied to the Nuclear Density Gauge
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 61-74
Technical Paper / Radioisotope / dx.doi.org/10.13182/NT71-A30902
Californium-252 Neutron Sources for Industrial Applications
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 75-83
Technical Paper / Radioisotope / dx.doi.org/10.13182/NT71-A30903
A Useful Recurrence Formula for the Equations of Radioactive Decay
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 84-88
Technical Paper / Radioisotope / dx.doi.org/10.13182/NT71-A30904
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 89-95
Technical Paper / Shielding / dx.doi.org/10.13182/NT71-A30905
Reciprocal Multiplication Meter
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 96-98
Technical Paper / Instrument / dx.doi.org/10.13182/NT71-A30906
Alpha-Particle Densitometer with Variable Response
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 99-104
Technical Paper / Instrument / dx.doi.org/10.13182/NT71-A30907
Exposure Angular Distributions in Air Above Disk Isotropic Cobalt-60 Sources
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 105-114
Technical Paper / Radiation / dx.doi.org/10.13182/NT71-A30908
An Equilibration Method for Measuring Low-Oxygen Activities in Liquid Sodium
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 115-119
Technical Paper / Analysis / dx.doi.org/10.13182/NT71-A30909
Measurement of Neutron Fluence by Neptunium-237 and Uranium-238 Fission Dosimeters
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 120-130
Technical Paper / Analysis / dx.doi.org/10.13182/NT71-A30910
Determination of Pyrocarbon Thermal Conductivity by the Burst-Reactor Technique
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 131-143
Technical Paper / Technique / dx.doi.org/10.13182/NT71-A30911
An Expository Derivation of Neutron Transport Equations
Nuclear Technology / Volume 11 / Number 1 / May 1971 / Pages 144-149
Technical Paper / Education / dx.doi.org/10.13182/NT71-A30912
An Analytical Reactor Excursion Model with Delayed Neutrons
Nuclear Technology / Volume 11 / Number 2 / June 1971 / Pages 159-174
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30881
Nuclear Technology / Volume 11 / Number 2 / June 1971 / Pages 175-184
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30882
Critical Experiments with Unmoderated Plutonium Oxide
Nuclear Technology / Volume 11 / Number 2 / June 1971 / Pages 185-190
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30883
A Capillary Valve for Use in the Ventilation of Fast Breeder Control Rods
Nuclear Technology / Volume 11 / Number 2 / June 1971 / Pages 191-205
Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A30884
Apparatus for Study of In-Pile Creep of Fuels
Nuclear Technology / Volume 11 / Number 2 / June 1971 / Pages 206-212
Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A30885
Nondestructive Testing of Encapsulated Radioactive Cesium and Strontium
Nuclear Technology / Volume 11 / Number 2 / June 1971 / Pages 213-221
Technical Paper / Radioactive Waste / dx.doi.org/10.13182/NT71-A30886
Selection of Steam Generator Tubing Material for the Westinghouse LMFBR Demonstration Plant
Nuclear Technology / Volume 11 / Number 2 / June 1971 / Pages 222-231
Technical Paper / Material / dx.doi.org/10.13182/NT71-A30887
Reentry Protection for Radioisotope Heat Sources
Nuclear Technology / Volume 11 / Number 2 / June 1971 / Pages 232-245
Technical Paper / Radioisotope / dx.doi.org/10.13182/NT71-A30888
A Calculation of Neutron-Induced Physical Doses in Human Tissues
Nuclear Technology / Volume 11 / Number 2 / June 1971 / Pages 246-258
Technical Paper / Radiation / dx.doi.org/10.13182/NT71-A30889
An In-Core Furnace for the High-Temperature Irradiation Testing of Reactor Fuels
Nuclear Technology / Volume 11 / Number 2 / June 1971 / Pages 259-265
Technical Paper / Technique / dx.doi.org/10.13182/NT71-A30890
An Inexpensive Pump for Liquid Sodium
Nuclear Technology / Volume 11 / Number 2 / June 1971 / Pages 266-267
Technical Note / Reactor / dx.doi.org/10.13182/NT71-A30891
Nuclear Technology / Volume 11 / Number 2 / June 1971 / Pages 268-269
Technical Note / Shielding / dx.doi.org/10.13182/NT71-A30892
The Soviet Program on Nuclear Explosives for the National Economy
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 280-302
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30862
The Use of Multiple Nuclear Explosives for Gas Stimulation
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 303-314
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30863
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 315-322
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30864
A Method for Estimating the Risk from a Plowshare Detonation
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 323-330
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30865
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 331-334
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30866
Radiological Considerations in the Use of Natural Gas from Nuclearly Stimulated Wells
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 335-344
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30867
Recovery of High-Viscosity Petroleum by Steam from Geothermal Heat
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 345-356
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30868
Neutron Shielding of Underground Nuclear Explosives
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 357-366
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30869
Leaching of Chalcopyrite (CuFeS2) with Sodium Chloride Sulfuric Acid Solutions
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 367-371
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30870
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 372-378
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30871
Microfracturing in Postshot Gasbuggy Core GB-3
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 379-389
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30872
The Chemistry of the Gasbuggy Chimney
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 390-399
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30873
On-Line Monitor of Natural Gas Lines for Hydrogen-3 and Krypton-85
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 400-405
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30874
Fate of Schooner Fallout Radionuclides Ingested by the Dairy Cow
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 406-412
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30875
Radionuclide Distribution in the Particle Population Produced by the Schooner Cratering Detonation
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 413-443
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30876
Biological Implications of Nuclear Debris in Aquatic Ecosystems
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 444-458
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30877
Distribution, Residence Time, and Inventory of Tritium in Sedan Crater Ejecta
Nuclear Technology / Volume 11 / Number 3 / July 1971 / Pages 459-465
Technical Paper / Nuclear Explosion Engineering / Nuclear Explosive / dx.doi.org/10.13182/NT71-A30878
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 474-478
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30844
Comparison of Rupture Data from Irradiated Fuel Rods and Unirradiated Cladding
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 479-490
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30845
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 491-501
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30846
Fuel Rod Failure Under Loss-of-Coolant Conditions in Treat
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 502-520
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30847
Application of Experimental Data to Analytical Evaluation of Cladding Failure Distribution
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 521-525
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30848
The Effects of Clad Swelling on Emergency Core Cooling Performance
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 526-531
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30849
The Effect of Zircaloy-Clad Fuel Rod Failure on BWR Core Spray Cooling
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 532-543
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30850
The Effect of Fuel Rod Failure on Emergency Core Cooling System Design for Boiling Water Reactors
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 544-550
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30851
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 551-556
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30852
Effect of Flow Blockage on Bottom Flooding Heat Transfer Effectiveness (Flecht)
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 557-562
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30853
Dynamic Neutronic and Mechanical Measurements with a Pulse Reactor of Uranium-Molybdenum Alloy
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 563-577
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Reactor / dx.doi.org/10.13182/NT71-A30854
Behavior of Mixed Oxide (U,Pu)O2 Fuels as a Function of Temperature and Burnup
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 578-591
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Fuel / dx.doi.org/10.13182/NT71-A30855
Through-Thickness Neutron Fluence and Embrittlement Gradients in Reactor Pressure Vessels
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 592-601
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Material / dx.doi.org/10.13182/NT71-A30856
Underwater Charging Machine for Nuclear Irradiation Sample Insertion
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 602-608
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Hot Laboratory / dx.doi.org/10.13182/NT71-A30857
New Encapsulation Techniques for the Fabrication of Californium-252 Neutron Sources
Nuclear Technology / Volume 11 / Number 4 / August 1971 / Pages 609-615
Technical Paper / Symposium on Fuel Rod Failure and Its Effect / Technique / dx.doi.org/10.13182/NT71-A30858