Number 1
- Table of Contents
- Authors
- Comments on “Realistic Estimates of the Consequences of Nuclear Accidents”
- Reply to “Comments on ‘Realistic Estimates of the Consequences of Nuclear Accidents’”
- Continuing Comments on “The Uncertainty in Accident Consequences Calculated by Large Codes Due to Uncertainties in Input”
- Reply to “Continuing Comments on ‘The Uncertainty in Accident Consequences Calculated by Large Codes Due to Uncertainties in Input’”
- Radiological Significance and Management of Tritium, Carbon-14, Krypton-85, Iodine-129 Arising from the Nuclear Fuel Cycle
- Multiphase Transport Fundamentals, Reactor Safety Applications
Joining Techniques for Core Flow Test Loop Fuel Rod Simulators
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 7-22
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32876
Instrument Fault Detection in a Pressurized Water Reactor Pressurizer
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 23-32
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32877
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 33-39
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32878
Analyzing the Rod Drop Accident in a Boiling Water Reactor
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 40-54
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32879
The Role of Plutonium-238 in Nuclear Fuel Cycles
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 55-71
Technical Paper | Fuel Cycle | doi.org/10.13182/NT82-A32880
Optimization of Fuel Cycle Strategies with Constraints on Uranium Availability
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 72-80
Technical Paper | Fuel Cycle | doi.org/10.13182/NT82-A32881
Irradiation Performance of Coated Fuel Particles with Fission Product Retaining Kernel Additives
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 81-92
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32882
Migration of Brine Inclusions in Salt
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 93-101
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32883
The Influence of Speciation on the Geospheric Migration of Radionuclides
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 102-105
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32884
Fuel Cycle Cost Considerations of Increased Discharge Burnups
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 106-111
Technical Paper | Economic | doi.org/10.13182/NT82-A32885
In-Reactor Measurement of Cladding Strain: Fuel Density and Relocation Effects
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 112-119
Technical Paper | Material | doi.org/10.13182/NT82-A32886
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 120-127
Technical Paper | Material | doi.org/10.13182/NT82-A32887
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 128-133
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT82-A32888
Downflow Post-Critical Heat Flux Heat Transfer to Low Pressure Water
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 134-140
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT82-A32889
Fast-Neutron Hodoscope at TREAT: Methods for Quantitative Determination of Fuel Dispersal
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 141-188
Technical Paper | Analyses | doi.org/10.13182/NT82-1
Number 2
- Table of Contents
- Authors
- Preface: Comparative Leaching Behavior of Radioactive Waste Forms
- Overview: Argonne Workshop on Comparative Leaching Behavior of Radioactive Waste Forms
- Thermal Analysis of Pressurized Water Reactors
- Physics of Modern Materials (Vols. I and II)
- Nuclear Disaster in the Urals
- Two-Phase Flow and Heat Transfer in the Power and Process Industries
- Theory of the Nuclear Shell Model
- Basic Elements of Light Water Reactor Fuel Rod Design
Application of Glass Corrosion Concepts to Nuclear Waste Immobilization
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 212-225
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32849
Continuous-Flow Leaching Studies of Crushed and Cored SYNROC
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 226-237
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32850
Mechanisms of Leaching and Dissolution of UO2 Fuel
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 238-253
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32851
Leach Testing of Idaho Chemical Processing Plant Final Waste Forms
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 254-264
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32852
Mechanisms That Control Aqueous Leaching of Nuclear Waste Glass
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 265-270
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32853
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 271-277
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32854
Comparative Leaching Behavior of SYNROC B and A Borosilicate Glass
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 278-288
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32855
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 289-296
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32856
A Criterion for Selecting Leach Test Specimen Sizes
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 297-300
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32857
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 301-305
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32858
MCC-1: A Standard Leach Test for Nuclear Waste Forms
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 306-309
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32859
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 313-321
Nuclear Safety | doi.org/10.13182/NT82-A32860
Fission Product Analytic Impulse Source Functions
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 322-339
Fuel Cycle | doi.org/10.13182/NT82-A32861
A Model for the Effective Thermal and Mechanical Properties of Cracked UO2 Pellets
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 340-350
Nuclear Fuel | doi.org/10.13182/NT82-A32862
Probabilistic Interpretation of Nuclear Waste Assay by Passive Gamma Technique
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 351-360
Radioactive Waste Management | doi.org/10.13182/NT82-A32863
Nuclear Waste Partitioning and Transmutation
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 361-371
Radioactive Waste Management | doi.org/10.13182/NT82-A32864
The Effect of Plant Reliability Improvement in the Cost of Generating Electricity
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 372-391
Economic | doi.org/10.13182/NT82-A32865
Estimate of Cross Flow in High Temperature Gas-Cooled Reactor Fuel Blocks
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 392-400
Heat Transfer and Fluid Flow | doi.org/10.13182/NT82-A32866
Radiation-Induced Outgassing from Sorption Pump Material
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Page 401
Technical Note | Material | doi.org/10.13182/NT82-A32867
Number 3
On the Behavior of Impregnated Charcoal Filters During a Two-Stage Accident
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 422-425
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32900
Transition Boiling Heat Transfer in the Semiscale Mod-3 Core During Reflood
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 426-433
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32901
Gap Conductance and Temperature Transients in Modified Pulse Design Experiments
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 434-446
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32902
Power Estimation in the Pressurized Water Reactor
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 447-453
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32903
Synthetic Fuel Production Using Texas Lignite and a Very High Temperature Reactor for Process Heat
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 454-464
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32904
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 465-477
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32905
Monitoring Krypton-85 During Three Mile Island Unit 2 Purging
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 478-483
Technical Paper | Nuclear Safety | doi.org/10.13182/NT82-A32906
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 484-492
Technical Paper | Nuclear Safety | doi.org/10.13182/NT82-A32907
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 493-506
Technical Paper | Nuclear Safety | doi.org/10.13182/NT82-A32908
Risk Assessment of Alternative Proliferation Routes
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 507-515
Technical Paper | Fuel Cycle | doi.org/10.13182/NT82-A32909
An Evaluation of Pressurized Water Reactor Frequent Refueling
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 516-526
Technical Paper | Fuel Cycle | doi.org/10.13182/NT82-A32910
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 527-534
Technical Paper | Chemical Processing | doi.org/10.13182/NT82-A32911
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 535-546
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32912
Development of High-Uranium-Loaded U3O8-Al Fuel Plates
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 547-552
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32913
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 553-564
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32914
The Possible Impact of Fuel Pellet Cracking on Inferred Gap Conductance and Fuel Stored Energy
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 565-574
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32915
Interactions of Backfill Materials with Cesium in a Bittern Brine Under Repository Conditions
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 575-579
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32916
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 580-590
Technical Paper | Radiation Biology and Environment | doi.org/10.13182/NT82-A32917
Determination of the Concentrations of Alpha-Emitting Isotopes
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 591-593
Technical Note | Analyse | doi.org/10.13182/NT82-A32918