Home / Publications / Journals / Nuclear Technology / Volume 49 / Number 1
Visual In-Pile Fuel Disruption Experiments
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 9-18
Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32501
Study of Progressive Damage to Reinforced Concrete Structures Submitted to Dynamic Reversed Load
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 19-26
Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32502
The Hydrodynamics of Large-Scale Fuel-Coolant Interactions
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 27-39
Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32503
Critical Experiments with Concrete-Reflected Fast Test Reactor Fuel Pins in Water
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 40-46
Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32504
Control of Oxygen, Hydrogen, and Tritium in Sodium Systems at Experimental Breeder Reactor II
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 47-50
Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32505
The Analysis of Boiling Water Reactor Long-Term Cooling
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 51-60
Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32506
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 61-69
Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32507
Acoustic Measurement of Penetration of Liquid Sodium into Limestone Concrete
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 70-79
Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32508
The Uncertainty in Accident Consequences Calculated by Large Codes due to Uncertainties in Input
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 80-91
Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32509
In-Reactor Measurement of Neutron Absorber Performance
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 92-101
Technical Paper / Nuclear Power Reactor Safety / Reactor / dx.doi.org/10.13182/NT80-A32510
Implications of In-Channel Plugging During Fast Reactor Overpower Excursions
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 102-114
Technical Paper / Nuclear Power Reactor Safety / Reactor Siting / dx.doi.org/10.13182/NT80-A32511
A Uranium-Plutonium-Neptunium Fuel Cycle to Produce Isotopically Denatured Plutonium
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 115-120
Technical Paper / Nuclear Power Reactor Safety / Fuel Cycle / dx.doi.org/10.13182/NT80-A32512
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 121-128
Technical Paper / Nuclear Power Reactor Safety / Chemical Processing / dx.doi.org/10.13182/NT80-A32513
Pellet and Sphere-Pac (U,Pu)C Fuel Comparative Irradiation Tests
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 129-135
Technical Paper / Nuclear Power Reactor Safety / Fuel / dx.doi.org/10.13182/NT80-A32514
Development and Irradiation Performance of Uranium Aluminide Fuels in Test Reactors
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 136-149
Technical Paper / Nuclear Power Reactor Safety / Fuel / dx.doi.org/10.13182/NT80-A32515
A Model for the Transport of Radionuclides and Their Decay Products Through Geologic Media
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 150-158
Technical Paper / Nuclear Power Reactor Safety / Radioactive Waste / dx.doi.org/10.13182/NT80-A32516
Intensity Measurements in X-Ray Fluorescence Analysis
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 159-164
Technical Paper / Nuclear Power Reactor Safety / Instrument / dx.doi.org/10.13182/NT80-A32517
Measurement of the Ge(Li) Detector Efficiency for Gas Bomb Geometries
Nuclear Technology / Volume 49 / Number 1 / June 1980 / Pages 165-173
Technical Paper / Nuclear Power Reactor Safety / Analysis / dx.doi.org/10.13182/NT80-A32518