Number 1
Irradiation Behavior of Experimental Mark-II Experimental Breeder Reactor II Driver Fuel
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 7-22
Technical Paper | Reactor | doi.org/10.13182/NT80-A32408
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 23-38
Technical Paper | Reactor | doi.org/10.13182/NT80-A32409
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 39-50
Technical Paper | Reactor | doi.org/10.13182/NT80-A32410
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 51-58
Technical Paper | Reactor | doi.org/10.13182/NT80-A32411
Development of a Dynamics Model for the Research Reactor Maria
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 59-69
Technical Paper | Reactor | doi.org/10.13182/NT80-A32412
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 70-90
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32413
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 91-109
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32414
Design Against Weathering of Iodine Filters
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 110-118
Technical Paper | Chemical Processing | doi.org/10.13182/NT80-A32415
Helium Fill Gas Absorption in Pressurized UO2 Fuel Rods During Irradiation
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 119-124
Technical Paper | Fuel | doi.org/10.13182/NT80-A32416
Heat Transfer in Pressurized Water Reactor Components Most Often Subject to Thermal Shock
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 125-152
Technical Paper | Fuel | doi.org/10.13182/NT80-A32417
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 153-162
Technical Paper | Fuel | doi.org/10.13182/NT80-A32418
Ocean Dumping of High-Level Waste—An Acceptable Solution We Can “Guarantee”
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 163-172
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32419
Laboratory Simulation of High-Level Liquid Waste Evaporation and Storage
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 173-180
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32420
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 181-188
Technical Paper | Material | doi.org/10.13182/NT80-A32421
Analysis of 60Co Gamma-Ray Transport Through Air by Discrete-Ordinates Transport Codes
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 189-199
Technical Paper | Shielding | doi.org/10.13182/NT80-A32422
Radiation Transport in Earth for Neutron and Gamma-Ray Point Sources Above an Air-Ground Interface
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 200-207
Technical Paper | Shielding | doi.org/10.13182/NT80-A32423
Determination of the Concentration of Solutes in Liquids by Means of the (n,α) and (n,γ) Reactions
Nuclear Technology | Volume 47 | Number 1 | January 1980 | Pages 208-212
Technical Paper | Analysis | doi.org/10.13182/NT80-A32424
Number 2
Accidental Criticality of a Fusion-Fission Hybrid Blanket Design
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 221-233
Technical Paper | Reactor | doi.org/10.13182/NT80-A32428
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 234-243
Technical Paper | Reactor | doi.org/10.13182/NT80-A32429
PLENUM-2A, A Program for Transient Analysis of Liquid-Metal Fast Breeder Reactor Outlet Plenums
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 244-265
Technical Paper | Reactor | doi.org/10.13182/NT80-A32430
Ultrasonic Inspection of Liquid-Metal Fast Breeder Reactor Steam Generator Duplex Tubing
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 257-267
Technical Paper | Reactor | doi.org/10.13182/NT80-A32431
Heat Transfer of a Spray Droplet in a Nuclear Reactor Containment
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 268-281
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32432
Containment Response to Postulated Core Meltdown Accidents in the Fast Flux Test Facility
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 282-307
Technical Paper | Reactor Siting | doi.org/10.13182/NT80-A32433
Evaporative Removal of Sodium from Reactor Components
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 308-311
Technical Paper | Fuel | doi.org/10.13182/NT80-A32434
Radionuclide Transport Through Heterogeneous Media
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 312-323
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32435
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 324-342
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32436
An Improved Evaluation Model for Zircaloy Oxidation
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 343-357
Technical Paper | Material | doi.org/10.13182/NT80-A32437
Gas Generation by Self-Radiolysis of Tritiated Waste Materials
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 358-362
Technical Paper | Material | doi.org/10.13182/NT80-A32438
Nuclear Technology | Volume 47 | Number 2 | February 1980 | Pages 363-377
Technical Paper | Analysis | doi.org/10.13182/NT80-A32439
Number 3
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 385-396
Technical Paper | Reactor | doi.org/10.13182/NT80-A32392
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 397-405
Technical Paper | Reactor | doi.org/10.13182/NT80-A32393
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 406-411
Technical Paper | Reactor | doi.org/10.13182/NT80-A32394
Shielding Calculations for the Tokamak Fusion Test Reactor Neutral Beam Injectors
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 412-420
Technical Paper | Reactor | doi.org/10.13182/NT80-A32395
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 421-435
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32396
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 436-443
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32397
Plutonium Fuel Cycles in the Spectral Shift Controlled Reactor
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 444-450
Technical Paper | Fuel Cycle | doi.org/10.13182/NT80-A32398
Confinement of Ruthenium Oxides Volatilized During Nuclear Fuels Reprocessing
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 451-456
Technical Paper | Chemical Processing | doi.org/10.13182/NT80-A32399
Uncertainty Analysis and Thermal Stored Energy Calculations in Nuclear Fuel Rods
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 457-467
Technical Paper | Fuel | doi.org/10.13182/NT80-A32400
Adsorption of Iodine Species with Ion Exchange Resins in Aqueous Solutions
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 468-476
Technical Paper | Radioactive Waste | doi.org/10.13182/NT80-A32401
The Oxidation Kinetics of Some Zirconium Alloys in Flowing Carbon Dioxide at High Temperatures
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 477-484
Technical Paper | Material | doi.org/10.13182/NT80-A32402
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 485-493
Technical Paper | Hot Laboratory | doi.org/10.13182/NT80-A32403
Boundary Conditions for the Geospheric Transport Equation
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 494-495
Technical Note | Radioactive Waste | doi.org/10.13182/NT80-A32404
The Effects of Fe-Ni-Co-V Structural Alloys on Fusion Reactor Neutronic Performance
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 496-498
Technical Note | Material | doi.org/10.13182/NT80-A32405