Number 1 | Number 2 | Number 3
A Mathematical Model for an Integral Economizer U-Tube Steam Generator
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 12-32
Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31847
Thermal Shock Effects in Fast Burst Reactors
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 33-39
Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31848
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 40-50
Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31849
Nuclear Analysis of a Tokamak Experimental Power Reactor Conceptual Design
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 51-79
Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31850
Migration of Metallic Fission Products in Reactor Oxide Fuels
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 80-86
Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31851
The Importance of Heat Transfer in Hypothetical Core Disruptive Accident Analysis
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 87-96
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT77-A31852
Basis for Subcritical Limits in Proposed Criticality Safety Standard for Mixed Oxides
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 97-111
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT77-A31853
Neutron Multiplication and Shielding Problems in Pressurized Water Reactor Spent Fuel Shipping Casks
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 112-118
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT77-A31854
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 119-130
Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31855
On the Pellet-Cladding Interaction Phenomenon
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 131-144
Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31856
Simulation Study of the Restructuring of Advanced Fuel Heated in a Radial Temperature Gradient
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 145-153
Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31857
Study of Uranium-Plutonium Carbide-Based Fuel Simulating High Burnup
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 154-161
Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31858
Simulation of the Nuclear Power Economy
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 162-172
Technical Paper / Economic / dx.doi.org/10.13182/NT77-A31859
Basic Compatibility Studies of Advanced Fuels with 3d Transition Metals
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 173-177
Technical Paper / Material / dx.doi.org/10.13182/NT77-A31860
Methods of Shield Analysis for Protection Against Electrons in Space
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 178-183
Technical Paper / Shielding / dx.doi.org/10.13182/NT77-A31861
On the Effective Temperature of an Expanding Tube with a Radial Temperature Gradient over the Wall
Nuclear Technology / Volume 35 / Number 1 / August 1977 / Pages 184-187
Technical Note / Reactor / dx.doi.org/10.13182/NT77-A31862
Processing and Composition Control of Weak-Acid-Resin-Derived Fuel Microspheres
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 217-226
Fabrication / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31881
Improved Gas Distributor for Coating High-Temperature Gas-Cooled Reactor Fuel Particles
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 227-237
Fabrication / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31882
Coated Fuel Particles: Requirements and Status of Fabrication Technology
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 238-245
Fabrication / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31883
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 246-253
Fabrication / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31884
Fundamentals on the Agglomerate Model and Its Relation to the Physical Properties of Pyrocarbon
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 257-262
Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31885
Coated Nuclear Fuel Particles: The Coating Process and Its Model
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 263-278
Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31886
Automatic Size Analysis of Coated Fuel Particles
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 279-283
Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31887
Quality Control Techniques for Pyrocarbon
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 284-292
Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31888
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 293-300
Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31889
Transmission Electron Microscopy of Pyrocarbon Coatings
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 301-309
Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31890
Influence of Porosity on the Irradiation Performance of Pyrocarbon Coatings
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 310-319
Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31891
Properties of Silicon Carbide for Nuclear Fuel Particle Coatings
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 320-336
Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31892
Preliminary Examination of the Helium Permeability of Pyrocarbon Coatings
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 337-339
Pyrocarbon / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31893
Properties Influencing High-Temperature Gas-Cooled Reactor Coated Fuel Particle Performance
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 343-352
Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31894
Neutron-Induced Permeability of Pyrocarbon-Coated High-Temperature Gas-Cooled Reactor Fuel Particles
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 353-358
Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31895
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 359-367
Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31896
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 368-378
Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31897
Improvement of a Method for Predicting Failure Rates of Coated Particles During Irradiation
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 379-385
Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31898
Restoration of Carbon Monoxide Equilibrium in Porous Oxide High-Temperature Reactor Fuel Particles
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 386-391
Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31899
Amoeba Behavior of UO2 Coated Particle Fuel
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 392-402
Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31900
Migration of ThO2 Kernels Under the Influence of a Temperature Gradient
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 403-412
Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31901
Silicon Carbide Corrosion in High-Temperature Gas-Cooled Reactor Fuel Particles
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 413-427
Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31902
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 428-441
Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT35-428
Irradiation Performance of Fort St. Vrain High-Temperature Gas-Cooled Reactor Fuel in Capsule F-30
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 442-454
Performance and Performance Modeling / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31904
Cesium Release and Transport in Biso-Coated Fuel Particles
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 457-464
Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31905
Cesium Release Data for Biso-Coated Particles
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 465-474
Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31906
Release of Metallic Fission Products from Multilayered Coated Particles
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 475-482
Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31907
Silver Release from Coated Particle Fuel
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 483-493
Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT35-483
Emission of Fission Gases by Failed Coated Oxide Fuel Particles
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 494-500
Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31909
Fission Gas Release from Fuel Particles and Fuel Rods
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 501-508
Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31910
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 509-515
Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31911
Release of Rare Fission Gases from Spherical Elements with Coated Fuel Particles
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 516-523
Fission Product Release / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31912
Chemical Vapor Deposition of ZrC Made by Reactions of ZrCl4 with CH4 and with C3H6
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 527-535
Advanced and Improved Fuel and Application / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31913
Improvements in the Performance of Nuclear Fuel Particles Offered by Silicon-Alloyed Carbon Coatings
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 536-547
Advanced and Improved Fuel and Application / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31914
Metallic Fission Product Retention of Coated Particles with Ceramic Kernel Additives
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 548-556
Advanced and Improved Fuel and Application / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31915
Coated Particle Fuel Element for Pressurized Water Reactors
Nuclear Technology / Volume 35 / Number 2 / September 1977 / Pages 557-563
Advanced and Improved Fuel and Application / Coated Particle Fuel / Fuel / dx.doi.org/10.13182/NT77-A31916
A Technical Scale Gas Generator for Steam Gasification of Coal Using Nuclear Heat
Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 581-590
Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31867
SOPHT—A Computer Model for CANDU-PHWR Heat Transport Networks and Their Control
Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 591-602
Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31868
Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 603-610
Technical Paper / Reactor / dx.doi.org/10.13182/NT77-A31869
Fission and Explosive Energy Releases of PuO2, PuO2-UO2, UO2, and UO3 Assemblies
Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 611-616
Technical Paper / Reactor Siting / dx.doi.org/10.13182/NT77-A31870
A Generalized Parametric Model for Transient Gas Release and Swelling in Oxide Fuels
Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 617-634
Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31871
Thorium-Based Fuels in Fast Breeder Reactors
Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 635-650
Technical Paper / Fuel / dx.doi.org/10.13182/NT77-A31872
Transport of Deuterium in Nb—1 wt% Zr
Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 651-655
Technical Paper / Material / dx.doi.org/10.13182/NT77-A31873
Interactions of Refractories and Reactor Materials with Sodium
Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 656-662
Technical Paper / Material / dx.doi.org/10.13182/NT77-A31874
In-Line Determination of Fissile Material in High-Activity Solutions
Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 663-670
Technical Paper / Technique / dx.doi.org/10.13182/NT77-A31875
Elastic-Plastic Analysis of Pressurized Ducts with Rounded Corners
Nuclear Technology / Volume 35 / Number 3 / October 1977 / Pages 671-676
Technical Note / Reactor / dx.doi.org/10.13182/NT77-A31876