Number 1
In-Line Vacuum-Distillation Sodium Sampler
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 7-11
Technical Paper | Reactor | 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 | 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 | doi.org/10.13182/NT71-A15893
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 26-30
Technical Paper | Chemical Processing | doi.org/10.13182/NT71-A15894
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 31-35
Technical Paper | Chemical Processing | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT71-A15903
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 119-126
Technical Paper | Nuclear Explosive | 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 | 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 | doi.org/10.13182/NT71-A15906
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 141-143
Technical Note | Radioisotope | doi.org/10.13182/NT71-A15907
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 144-145
Department | Book Review | doi.org/10.13182/NT71-A15909
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Page 144
Department | Book Review | doi.org/10.13182/NT71-A15908
Nuclear Technology | Volume 12 | Number 1 | September 1971 | Pages 145-146
Department | Book Review | 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 | doi.org/10.13182/NT71-A15911
Number 2
- Table of Contents
- Authors
- Topics in Light Water Reactor Physics: Final Report of the NORA Project
- Basic Thermodynamics
- Neutron Capture Gamma-Ray Spectroscopy
- A. Plasma Physics and Controlled Nuclear Fusion Research, Vol. I, B. Plasma Physics and Controlled Nuclear Fusion Research, Vol. II and C. Nuclear Fusion—Special Supplement 1970 World Survey of Major Facilities in Controlled Fusion
- Handling of Nuclear Information
- Decontamination of Nuclear Reactors and Equipment
- A. Radioisotope X-Ray Fluorescence Spectrometry, B. Neutron Moisture Gauges and C. Monitoring of Radioactive Contamination on Surfaces
- The Water Encyclopedia
- Quantum Fluids
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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT71-A31029
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 226-234
Technical Paper | Analysis | 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 | 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 | 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 | doi.org/10.13182/NT71-A31033
Number 3
Enriched Uranium Metal Criticality Calculations
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 260-268
Technical Paper | Reactor | doi.org/10.13182/NT71-A31005
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 269-275
Technical Paper | Reactor | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT71-A31012
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 320-323
Technical Note | Reactor | 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 | 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 | doi.org/10.13182/NT71-A31015
Number 4
- Table of Contents
- Authors
- Nuclear Reactor Theory
- Dynamics of Nuclear Reactors
- Directory of Whole-Body Radioactivity Monitors
- Publications Compiled by Staff Editors of IAEA
- Isotope Techniques for Studying Animal Protein Production from Non-Protein Nitrogen
- Isotopes and Radiation in Parasitology—II
- Microbiological Specifications and Testing Methods for Irradiated Foods
- Nuclear Accident Dosimetry
- Manual of Dosimetry in Radiotherapy
- Neutron Fluence Measurements
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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT71-A30992