Number 1 | Number 2 | Number 3
Post-Shutdown Surges in Cover Gas Activity in Experimental Breeder Reactor II (EBR-II)
Nuclear Technology / Volume 13 / Number 1 / January 1972 / Pages 6-19
Technical Paper / Reactor / dx.doi.org/10.13182/NT72-A31062
Linear Extrapolation Distances for Centrally and Eccentrically Located Control Rods
Nuclear Technology / Volume 13 / Number 1 / January 1972 / Pages 20-28
Technical Paper / Reactor / dx.doi.org/10.13182/NT72-A31063
Application of Nitride-Forming Reactions to Reprocessing of Spent Nuclear Fuels
Nuclear Technology / Volume 13 / Number 1 / January 1972 / Pages 29-35
Technical Paper / Fuel / dx.doi.org/10.13182/NT72-A31064
Interchannel Mixing in Wire Wrapped Liquid Metal Fast Reactor Fuel Assemblies
Nuclear Technology / Volume 13 / Number 1 / January 1972 / Pages 36-52
Technical Paper / Fuel / dx.doi.org/10.13182/NT72-A31065
Economic Analysis of the Nuclear Fuel Cycle
Nuclear Technology / Volume 13 / Number 1 / January 1972 / Pages 53-64
Technical Paper / Economic / dx.doi.org/10.13182/NT72-A31066
Investigation of Fluorine Deposits on Zircaloy Surfaces by Proton Activation
Nuclear Technology / Volume 13 / Number 1 / January 1972 / Pages 65-71
Technical Paper / Material / dx.doi.org/10.13182/NT72-A31067
Economics of Radiation Versus Heat-Catalyst Curing for Wood-Plastic Flooring Plant
Nuclear Technology / Volume 13 / Number 1 / January 1972 / Pages 72-77
Technical Paper / Radioisotope / dx.doi.org/10.13182/NT72-A31068
Production of Plutonium-238 with Minimum Plutonium-236 Contamination
Nuclear Technology / Volume 13 / Number 1 / January 1972 / Pages 78-82
Technical Paper / Radioisotope / dx.doi.org/10.13182/NT72-A31069
In-Phantom Dosimetry of Plutonium-238 Circulatory Support Heat Sources
Nuclear Technology / Volume 13 / Number 1 / January 1972 / Pages 83-94
Technical Paper / Radioisotope / dx.doi.org/10.13182/NT72-A31070
Extension of the Dual Spectrum Fuel Assay Concept
Nuclear Technology / Volume 13 / Number 1 / January 1972 / Pages 95-98
Technical Paper / Technique / dx.doi.org/10.13182/NT72-A31071
Thermal Densification of Austenitic Stainless Steel
Nuclear Technology / Volume 13 / Number 1 / January 1972 / Pages 99-102
Technical Note / Material / dx.doi.org/10.13182/NT72-A31072
Neutron Activation Analysis Using Daughter Activity
Nuclear Technology / Volume 13 / Number 1 / January 1972 / Pages 103-105
Technical Note / Analysis / dx.doi.org/10.13182/NT72-A31073
The Breeding Ratio with Correlation to Doubling Time and Fuel Cycle Reactivity Variation
Nuclear Technology / Volume 13 / Number 2 / February 1972 / Pages 114-130
Technical Paper / Reactor / dx.doi.org/10.13182/NT72-A31047
Models for the Safe Storage of Fissile Metal
Nuclear Technology / Volume 13 / Number 2 / February 1972 / Pages 131-147
Technical Paper / Reactor / dx.doi.org/10.13182/NT72-A31048
The CUSP Process for Preparing Concentrated, Crystalline Urania Sols by Solvent Extraction
Nuclear Technology / Volume 13 / Number 2 / February 1972 / Pages 148-158
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT72-A31049
Radiolysis of Hanford B Plant HDEHP Extractant
Nuclear Technology / Volume 13 / Number 2 / February 1972 / Pages 159-167
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT72-A31050
Studies of Fuel-Clad Mechanical Interaction and the Resulting Interaction Failure Mechanism
Nuclear Technology / Volume 13 / Number 2 / February 1972 / Pages 168-176
Technical Paper / Fuel / dx.doi.org/10.13182/NT72-A31051
Instrumented Capsule for Measuring Fission-Induced Creep of Oxide Fuels
Nuclear Technology / Volume 13 / Number 2 / February 1972 / Pages 177-184
Technical Paper / Fuel / dx.doi.org/10.13182/NT72-A31052
Elevated-Temperature Damage Functions for Neutron Embrittlement in Pressure Vessel Steels
Nuclear Technology / Volume 13 / Number 2 / February 1972 / Pages 185-193
Technical Paper / Material / dx.doi.org/10.13182/NT72-A31053
A Radioisotope-Fueled Stirling Engine Artificial Heart System
Nuclear Technology / Volume 13 / Number 2 / February 1972 / Pages 194-208
Technical Paper / Radioisotope / dx.doi.org/10.13182/NT72-A31054
Nuclear Technology / Volume 13 / Number 2 / February 1972 / Pages 209-215
Technical Paper / Shielding / dx.doi.org/10.13182/NT72-A31055
Heavy Element Analysis by Isotope-Excited X-Ray Fluoresence
Nuclear Technology / Volume 13 / Number 2 / February 1972 / Pages 216-224
Technical Paper / Analysis / dx.doi.org/10.13182/NT72-A31056
Impurity Effects on the Swelling of Irradiated Aluminum Oxide
Nuclear Technology / Volume 13 / Number 2 / February 1972 / Pages 225-226
Technical Note / Material / dx.doi.org/10.13182/NT72-A31057
Radiation Level Buildup on Plant Piping During Second Core Operation of Shippingport Plant
Nuclear Technology / Volume 13 / Number 3 / March 1972 / Pages 235-240
Technical Paper / Reactor / dx.doi.org/10.13182/NT72-A31077
A Systematic Procedure for Reactor Control System Design
Nuclear Technology / Volume 13 / Number 3 / March 1972 / Pages 241-249
Technical Paper / Reactor / dx.doi.org/10.13182/NT72-A31078
A Noise Technique for Measuring Reactivity Independent of the Neutron Generation Time
Nuclear Technology / Volume 13 / Number 3 / March 1972 / Pages 250-256
Technical Paper / Reactor / dx.doi.org/10.13182/NT72-A31079
Nuclear Technology / Volume 13 / Number 3 / March 1972 / Pages 257-263
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT72-A31080
The Chemical Characterization of Uranium Nitrides
Nuclear Technology / Volume 13 / Number 3 / March 1972 / Pages 264-272
Technical Paper / Fuel / dx.doi.org/10.13182/NT72-A31081
Nuclear Technology / Volume 13 / Number 3 / March 1972 / Pages 273-283
Technical Paper / Material / dx.doi.org/10.13182/NT72-A31082
An Improved Cold Trap for Sodium Systems
Nuclear Technology / Volume 13 / Number 3 / March 1972 / Pages 284-288
Technical Paper / Material / dx.doi.org/10.13182/NT72-A31083
Electrochemical Measurement of the Solubility of Carbon in Sodium
Nuclear Technology / Volume 13 / Number 3 / March 1972 / Pages 289-296
Technical Paper / Material / dx.doi.org/10.13182/NT72-A31084
Continuous Removal of Fission Products in a Nitride-Fueled Reactor
Nuclear Technology / Volume 13 / Number 3 / March 1972 / Pages 297-300
Technical Note / Chemical Processing / dx.doi.org/10.13182/NT72-A31085
Thermal Expansion Coefficients for Sodium-Potassium Liquid Alloys
Nuclear Technology / Volume 13 / Number 3 / March 1972 / Pages 301-302
Technical Note / Material / dx.doi.org/10.13182/NT72-A31086