Number 1 | Number 2 | Number 3
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 / dx.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 / dx.doi.org/10.13182/NT82-A32877
Nuclear Technology / Volume 56 / Number 1 / January 1982 / Pages 33-39
Technical Paper / Fission Reactor / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT82-A32886
Nuclear Technology / Volume 56 / Number 1 / January 1982 / Pages 120-127
Technical Paper / Material / dx.doi.org/10.13182/NT82-A32887
Nuclear Technology / Volume 56 / Number 1 / January 1982 / Pages 128-133
Technical Paper / Heat Transfer and Fluid Flow / dx.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 / dx.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 / dx.doi.org/10.13182/NT82-1
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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT82-A32853
Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 271-277
Technical Paper / Radioactive Waste Management / dx.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 / dx.doi.org/10.13182/NT82-A32855
Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 289-296
Technical Paper / Radioactive Waste Management / dx.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 / dx.doi.org/10.13182/NT82-A32857
Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 301-305
Technical Paper / Radioactive Waste Management / dx.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 / dx.doi.org/10.13182/NT82-A32859
Nuclear Technology / Volume 56 / Number 2 / February 1982 / Pages 313-321
Nuclear Safety / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT82-A32867
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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT82-A32904
Nuclear Technology / Volume 56 / Number 3 / March 1982 / Pages 465-477
Technical Paper / Fission Reactor / dx.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 / dx.doi.org/10.13182/NT82-A32906
Nuclear Technology / Volume 56 / Number 3 / March 1982 / Pages 484-492
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT82-A32907
Nuclear Technology / Volume 56 / Number 3 / March 1982 / Pages 493-506
Technical Paper / Nuclear Safety / dx.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 / dx.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 / dx.doi.org/10.13182/NT82-A32910
Nuclear Technology / Volume 56 / Number 3 / March 1982 / Pages 527-534
Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT82-A32911
Nuclear Technology / Volume 56 / Number 3 / March 1982 / Pages 535-546
Technical Paper / Nuclear Fuel / dx.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 / dx.doi.org/10.13182/NT82-A32913
Nuclear Technology / Volume 56 / Number 3 / March 1982 / Pages 553-564
Technical Paper / Nuclear Fuel / dx.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 / dx.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 / dx.doi.org/10.13182/NT82-A32916
Nuclear Technology / Volume 56 / Number 3 / March 1982 / Pages 580-590
Technical Paper / Radiation Biology and Environment / dx.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 / dx.doi.org/10.13182/NT82-A32918