Number 1 | Number 2 | Number 3
A Model of the Dynamic Behavior of the Coaxial-Flow Gaseous-Core Nuclear Reactor
Nuclear Technology / Volume 20 / Number 1 / October 1973 / Pages 5-14
Technical Paper / Reactor / dx.doi.org/10.13182/NT73-A31329
On the Emission Coefficient of Uranium Plasmas
Nuclear Technology / Volume 20 / Number 1 / October 1973 / Pages 15-26
Technical Paper / Reactor / dx.doi.org/10.13182/NT73-A31330
Effect of Neutron Irradiation on the Elastic Constants of Type-304 Stainless Steel
Nuclear Technology / Volume 20 / Number 1 / October 1973 / Pages 27-34
Technical Paper / Materials / dx.doi.org/10.13182/NT73-2
Radiation Doses from Hypothetical Exposures to Rulison Gas
Nuclear Technology / Volume 20 / Number 1 / October 1973 / Pages 35-50
Technical Paper / Nuclear Explosive / dx.doi.org/10.13182/NT73-A31332
Nuclear Technology / Volume 20 / Number 1 / October 1973 / Pages 51-59
Technical Paper / Instrument / dx.doi.org/10.13182/NT73-A31333
Continuous Conversion of Uranium/Plutonium Nitrates to Oxides
Nuclear Technology / Volume 20 / Number 1 / October 1973 / Pages 60-63
Technical Note / Chemical Processing / dx.doi.org/10.13182/NT73-A31334
Proton Dosimeter Design for Distributed Body Organs
Nuclear Technology / Volume 20 / Number 1 / October 1973 / Pages 64-67
Technical Note / Instrument / dx.doi.org/10.13182/NT73-A31335
Spectral Analysis of Sampled Nuclear Reactor Plant Data with Heterodyne Digital Filtering Techniques
Nuclear Technology / Volume 20 / Number 2 / November 1973 / Pages 79-85
Technical Paper / Reactor / dx.doi.org/10.13182/NT73-A31343
Determination of Optimum Fuel Loadings in Pressurized Water Reactors Using Dynamic Programming
Nuclear Technology / Volume 20 / Number 2 / November 1973 / Pages 86-102
Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT73-A31344
UO2 Pellet-Stack Shortening in a Boiling Water Reactor
Nuclear Technology / Volume 20 / Number 2 / November 1973 / Pages 103-108
Technical Paper / Fuel / dx.doi.org/10.13182/NT73-A31345
Use of Metallic Thorium for LWBRs and LWRs
Nuclear Technology / Volume 20 / Number 2 / November 1973 / Pages 109-113
Technical Paper / Fuel / dx.doi.org/10.13182/NT73-A31346
First Report on Apparatus to Simulate In-Reactor Transient Heating Conditions in Oxide Fuel Columns
Nuclear Technology / Volume 20 / Number 2 / November 1973 / Pages 114-123
Technical Paper / Fuel / dx.doi.org/10.13182/NT73-A31347
Californium-252 Assay System for FBR-Type Fuel Pins
Nuclear Technology / Volume 20 / Number 2 / November 1973 / Pages 124-133
Technical Paper / Analysis / dx.doi.org/10.13182/NT73-A31348
Effect of Minor Alloy Variations on the Thermal Densification of Austenitic Stainless Steels
Nuclear Technology / Volume 20 / Number 2 / November 1973 / Pages 134-135
Technical Note / Material / dx.doi.org/10.13182/NT73-A31349
Nuclear Power Plant Heat Rejection in an Arid Climate
Nuclear Technology / Volume 20 / Number 3 / December 1973 / Pages 140-148
Technical Paper / Reactor / dx.doi.org/10.13182/NT73-A31353
Methods for Calculating Vapor and Fuel Transport to the Secondary Containment in an LMFBR Accident
Nuclear Technology / Volume 20 / Number 3 / December 1973 / Pages 149-160
Technical Paper / Reactor / dx.doi.org/10.13182/NT73-A31354
A Review of Fusion-Fission (Hybrid) Concepts
Nuclear Technology / Volume 20 / Number 3 / December 1973 / Pages 161-178
Technical Paper / Reactors / dx.doi.org/10.13182/NT73-1
Storage Capacity for Fissile Material as a Function of Facility Size
Nuclear Technology / Volume 20 / Number 3 / December 1973 / Pages 179-189
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT73-A31356
Oxygen Interactions Between Sodium and Uranium-Plutonium Oxide Fuel
Nuclear Technology / Volume 20 / Number 3 / December 1973 / Pages 190-199
Technical Paper / Fuel / dx.doi.org/10.13182/NT73-A31357
A High-Capacity Annular Centrifugal Contactor
Nuclear Technology / Volume 20 / Number 3 / December 1973 / Pages 200-202
Technical Note / Chemical Processing / dx.doi.org/10.13182/NT73-A31358