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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT80-A32506
Nuclear Technology | Volume 49 | Number 1 | June 1980 | Pages 61-69
Technical Paper | Nuclear Power Reactor Safety / Reactor | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT80-A32518
Number 2
Liquid-Metal Fast Breeder Reactor Vented Assembly Hydraulic Modeling and Testing
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 186-195
Technical Paper | Reactor | doi.org/10.13182/NT80-A32481
A Continuous Glass Melter for Immobilization of Radioactive Waste
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 196-208
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32482
The Fixation of Radioiodine with Portland Cement. Part II: Radiation Stability Tests
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 209-213
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32483
Dynamic Process Model of a Plutonium Oxalate Precipitator
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 214-222
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32484
Alpha Waste Production and Proliferation Hazard of Different Fuel Cycles
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 223-232
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32485
A Production Facility for the Solidification of High-Level Radioactive Wastes
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 233-242
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32486
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 243-252
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32487
The Sorption of Technetium and Iodine Radioisotopes by Various Minerals
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 253-266
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32488
Full-Scale In-Can Melting for Vitrification of Nuclear Wastes
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 267-273
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32489
Spent Fuel Heatup Following Loss of Water During Storage
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 274-294
Nuclear Fuel Cycle | Fuel Cycle | doi.org/10.13182/NT80-A32490
Protection of Nuclear Power Plants Against Seism
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 295-306
Nuclear Fuel Cycle | Reactor | doi.org/10.13182/NT80-A32491
The Use of Yttrium for the Recovery of Tritium from Lithium at Low Concentrations
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 307-314
Nuclear Fuel Cycle | Chemical Processing | doi.org/10.13182/NT80-A32492
BeH2 as a Moderator in Minimum Critical Mass Systems
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 315-320
Technical Note | Reactor | doi.org/10.13182/NT80-A32493
Application of Sol-Gel Technology to Fixation of Nuclear Reactor Waste
Nuclear Technology | Volume 49 | Number 2 | July 1980 | Pages 321-324
Technical Note | Radioactive Waste | doi.org/10.13182/NT80-A32494
Number 3
Quality Influence on the Departure from Nucleate Boiling in Cross Flows Through Bundles
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 337-346
Technical Paper | Reactor | doi.org/10.13182/NT80-A17682
Thermomechanical Dynamic Behavior of the Solid Wall of a Pellet Fusion Reactor
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 347-359
Technical Paper | Reactor | doi.org/10.13182/NT80-A17683
Reduced Scale Simulations of Boiling Water Reactor Pool Swell: Some Limitations to the Scaling Laws
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 360-373
Technical Paper | Reactor | doi.org/10.13182/NT80-A17684
Some Comparisons Between Small-Scale Pool Swell Experiments and Model Predictions
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 374-379
Technical Paper | Reactor | doi.org/10.13182/NT80-A17685
Film Boiling and Vapor Explosion Phenomena
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 380-391
Technical Paper | Reactor | doi.org/10.13182/NT49-380
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 392-399
Technical Paper | Reactor | doi.org/10.13182/NT80-A17687
Optimal Size and Location of Nuclear Power Plants in Energy Parks
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 400-409
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A17688
Evaluation Models for Uranium Exploration by Active Neutron Logging
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 410-425
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A17689
Fuel Survey in the Light Water Reactors Based on the Activity of the Fission Products
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 426-434
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A17690
Two Near-Term Alternatives for Improved Nuclear Fuel Utilization
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 435-442
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A17691
On-Line Radiation Monitoring at a Nuclear Fuel Reprocessing Plant
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 443-457
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A17692
Hybrids for Direct Enrichment and Self-Protected Fissile Fuel Production
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 458-468
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A17693
Volume Reduction of Organic Alpha Waste by Pyrohydrolysis
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 469-473
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A17694
The Sorption of Actinides in Igneous Rocks
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 474-480
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A17695
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 481-491
Technical Paper | Material | doi.org/10.13182/NT80-A17696
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 492-497
Technical Paper | Material | doi.org/10.13182/NT80-A17697
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 498-503
Technical Note | Material | doi.org/10.13182/NT80-A17698
Nuclear Technology | Volume 49 | Number 3 | August 1980 | Pages 504-509
Technical Note | Instrument | doi.org/10.13182/NT80-A17699