Number 1 | Number 2 | Number 3 | Number 4
In-Line Vacuum-Distillation Sodium Sampler
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 7-11
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A15891
How to Make a Profit on Waste Heat
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 12-17
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A15892
Optimization of Nuclear Materials Safeguards Sampling Systems by Dynamic Programming
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 18-25
Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT71-A15893
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 26-30
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT71-A15894
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 31-35
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT71-A15895
An Investigation of Fast-Reactor Fuel Testing in a Thermal Reactor Core
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 36-45
Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A15896
Reactor Fuel Management Optimization in a Dynamic Environment
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 46-55
Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A15897
Surface Heat Flux for Incipient Boiling in Liquid Metal Heat Pipes
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 56-62
Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A15898
Gas-Cooled Fast Breeder Reactor Fuel Rod Design Considerations
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 63-68
Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A15899
Status of the Waste Solidification Demonstration Program
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 69-82
Technical Paper / Radioactive Waste / dx.doi.org/10.13182/NT71-A15900
Measurement of Cesium Sorption Isotherms in Liquid Sodium
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 83-92
Technical Paper / Material / dx.doi.org/10.13182/NT71-A15901
Carbon-Carbon Materials for Ablative Environments
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 93-107
Technical Paper / Material / dx.doi.org/10.13182/NT71-A15902
Reliability of Fluence-Embrittlement Projections for Pressure Vessel Surveillance Analyses
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 108-118
Technical Paper / Material / dx.doi.org/10.13182/NT71-A15903
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 119-126
Technical Paper / Nuclear Explosive / dx.doi.org/10.13182/NT71-A15904
Subliming Nuclear Microthruster and Its Space Applications
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 127-136
Technical Paper / Aerospace / dx.doi.org/10.13182/NT71-A15905
Effect of Gamma Radiation on LMFBR Subcriticality Measurements Using Noise Analysis
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 137-140
Technical Note / Reactor / dx.doi.org/10.13182/NT71-A15906
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 141-143
Technical Note / Radioisotope / dx.doi.org/10.13182/NT71-A15907
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Page 144
Department / Book Review / dx.doi.org/10.13182/NT71-A15908
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 144-145
Department / Book Review / dx.doi.org/10.13182/NT71-A15909
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Pages 145-146
Department / Book Review / dx.doi.org/10.13182/NT71-A15910
Alkali Metal Handling and Systems Operation Techniques
Nuclear Technology / Volume 12 / Number 1 / September 1971 / Page 146
Department / Book Review / dx.doi.org/10.13182/NT71-A15911
Evaluation of Critical Mass for Open-Cycle Gas-Core Rocket Reactors
Nuclear Technology / Volume 12 / Number 2 / October 1971 / Pages 152-161
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A31023
Anomalies in the Analysis of Air-Spaced Arrays
Nuclear Technology / Volume 12 / Number 2 / October 1971 / Pages 162-172
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A31024
A Risk Estimate for an Urban-Sited Reactor
Nuclear Technology / Volume 12 / Number 2 / October 1971 / Pages 173-184
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT71-A31025
Pressure Equalization System for Gas-Cooled Fast Breeder Reactor Fuel Elements
Nuclear Technology / Volume 12 / Number 2 / October 1971 / Pages 185-193
Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A31026
An Analytic Model for the Prediction of In-Pile Behavior of Oxide Fuel Rods
Nuclear Technology / Volume 12 / Number 2 / October 1971 / Pages 194-208
Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A31027
Estimates of Fuel Containment in a Coaxial Flow Gas-Core Nuclear Rocket
Nuclear Technology / Volume 12 / Number 2 / October 1971 / Pages 209-217
Technical Paper / Aerospace / dx.doi.org/10.13182/NT71-A31028
A Hydrogen Monitor for Detection of Leaks in LMFBR Steam Generators
Nuclear Technology / Volume 12 / Number 2 / October 1971 / Pages 218-225
Technical Paper / Instrument / dx.doi.org/10.13182/NT71-A31029
Nuclear Technology / Volume 12 / Number 2 / October 1971 / Pages 226-234
Technical Paper / Analysis / dx.doi.org/10.13182/NT71-A31030
Experimental Measurement of Gamma Heat in the High Flux Isotope Reactor
Nuclear Technology / Volume 12 / Number 2 / October 1971 / Pages 235-240
Technical Paper / Technique / dx.doi.org/10.13182/NT71-A31031
Safety Considerations for Recharge of THOR Spent Fuels in ZPRL
Nuclear Technology / Volume 12 / Number 2 / October 1971 / Pages 241-242
Technical Note / Reactor / dx.doi.org/10.13182/NT71-A31032
Investigation of a Device Using Radiation to Charge and Collect Particulate Matter
Nuclear Technology / Volume 12 / Number 2 / October 1971 / Pages 243-245
Technical Note / Radioisotope / dx.doi.org/10.13182/NT71-A31033
Enriched Uranium Metal Criticality Calculations
Nuclear Technology / Volume 12 / Number 3 / November 1971 / Pages 260-268
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A31005
Nuclear Technology / Volume 12 / Number 3 / November 1971 / Pages 269-275
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A31006
A Practical Approach to Nuclear Criticality Safety II—Critique of a Model
Nuclear Technology / Volume 12 / Number 3 / November 1971 / Pages 276-280
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A31007
Probability Treatment of Atmospheric Dispersion for Dose Calculations
Nuclear Technology / Volume 12 / Number 3 / November 1971 / Pages 281-289
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT71-A31008
Safeguards Inspection—An Analysis of Detection Methods and Diversion Strategies
Nuclear Technology / Volume 12 / Number 3 / November 1971 / Pages 290-297
Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT71-A31009
In-Flight Coolant Management Considerations for the NERVA Reactor Cooldown
Nuclear Technology / Volume 12 / Number 3 / November 1971 / Pages 298-306
Technical Paper / Aerospace / dx.doi.org/10.13182/NT71-A31010
Density Determinations of Alkali Metals by a Gamma Radiation Attenuation Technique
Nuclear Technology / Volume 12 / Number 3 / November 1971 / Pages 307-313
Technical Paper / Technique / dx.doi.org/10.13182/NT71-A31011
Two Methods of Determining ppm Quantities of Plutonium-236 in Plutonium-238
Nuclear Technology / Volume 12 / Number 3 / November 1971 / Pages 314-319
Technical Paper / Technique / dx.doi.org/10.13182/NT71-A31012
Nuclear Technology / Volume 12 / Number 3 / November 1971 / Pages 320-323
Technical Note / Reactor / dx.doi.org/10.13182/NT71-A31013
Effects of Different Fission Products in the Beta-Gamma Autoradiography
Nuclear Technology / Volume 12 / Number 3 / November 1971 / Pages 324-328
Technical Note / Fuel / dx.doi.org/10.13182/NT71-A31014
A Study of Mine Detection by Means of Neutron-Induced Gamma Rays
Nuclear Technology / Volume 12 / Number 3 / November 1971 / Pages 329-331
Technical Note / Radioisotope / dx.doi.org/10.13182/NT71-A31015
Minimum Critical Mass of Uranium-235 Reflected by Natural Uranium in Water
Nuclear Technology / Volume 12 / Number 4 / December 1971 / Pages 342-347
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30982
Analysis of Mechanical Work Energy for LMFBR Maximum Accidents
Nuclear Technology / Volume 12 / Number 4 / December 1971 / Pages 348-355
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30983
Static and Pulsed Reactivity Measurements on Large Uranium-235 Fuel Forms in Water
Nuclear Technology / Volume 12 / Number 4 / December 1971 / Pages 356-362
Technical Paper / Reactor / dx.doi.org/10.13182/NT71-A30984
The Utility of Ice Cubes as an Absorbent for Gaseous Fission Products
Nuclear Technology / Volume 12 / Number 4 / December 1971 / Pages 363-366
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT71-A30985
Melting Heat Rating of UO2-25 wt% PuO2 Fuels
Nuclear Technology / Volume 12 / Number 4 / December 1971 / Pages 367-374
Technical Paper / Fuel / dx.doi.org/10.13182/NT71-A30986
Semiempirical Formulas for Gamma-Ray Dose Rates Through Two-Layer Slab Shields
Nuclear Technology / Volume 12 / Number 4 / December 1971 / Pages 375-380
Technical Paper / Shielding / dx.doi.org/10.13182/NT71-A30987
Activation Analysis of Sodium and Potassium in Solid Propellants
Nuclear Technology / Volume 12 / Number 4 / December 1971 / Pages 381-387
Technical Paper / Analysis / dx.doi.org/10.13182/NT71-A30988
Characterization of a Diffusion Tube Hydrogen Detector in a Dynamic Sodium System
Nuclear Technology / Volume 12 / Number 4 / December 1971 / Pages 388-392
Technical Paper / Analysis / dx.doi.org/10.13182/NT71-A30989
Thermal Contact Resistance by Reflection of Heat Diffusion Waves
Nuclear Technology / Volume 12 / Number 4 / December 1971 / Pages 393-403
Technical Paper / Technique / dx.doi.org/10.13182/NT71-A30990
Comparison of Stainless Steel and Zircaloy-2 as Encapsulation Materials for Californium-252
Nuclear Technology / Volume 12 / Number 4 / December 1971 / Pages 404-406
Technical Note / Material / dx.doi.org/10.13182/NT71-A30991
Development of a Method of Neutron Radiography of Mixed Oxide Fuels Using Radiographic Analogs
Nuclear Technology / Volume 12 / Number 4 / December 1971 / Pages 407-414
Technical Note / Analysis / dx.doi.org/10.13182/NT71-A30992