Number 1 | Number 2 | Number 3
A Dynamic Model for Predicting CANDU Pressurizer Performance
Nuclear Technology / Volume 72 / Number 1 / January 1986 / Pages 7-23
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33747
Some Transient Characteristics of PIUS
Nuclear Technology / Volume 72 / Number 1 / January 1986 / Pages 24-33
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33748
Analytical Simulation of Boiling Water Reactor Pressure Suppression Pool Swell
Nuclear Technology / Volume 72 / Number 1 / January 1986 / Pages 34-38
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT86-A33749
Iodine-131 Species in the Stack Exhaust Air of Light Water Reactors
Nuclear Technology / Volume 72 / Number 1 / January 1986 / Pages 39-43
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT86-A33750
Investigations on the Retention of Elemental Radioiodine by Activated Carbons at High Temperatures
Nuclear Technology / Volume 72 / Number 1 / January 1986 / Pages 44-48
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT86-A33751
Nuclear Technology / Volume 72 / Number 1 / January 1986 / Pages 49-58
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT86-A33752
Development and Fabrication of 70% PuC—30% UC Fuel for the Fast Breeder Test Reactor in India
Nuclear Technology / Volume 72 / Number 1 / January 1986 / Pages 59-69
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT86-A33753
A New Gaseous Gap Conductance Relationship
Nuclear Technology / Volume 72 / Number 1 / January 1986 / Pages 70-74
Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT86-A33754
Nuclear Technology / Volume 72 / Number 1 / January 1986 / Pages 75-83
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT86-A33755
Volatilization of Cesium from Nuclear Waste Glass in a Canister
Nuclear Technology / Volume 72 / Number 1 / January 1986 / Pages 84-88
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT86-A33756
Nuclear Technology / Volume 72 / Number 1 / January 1986 / Pages 89-98
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT86-A33757
Derivative Method for Edge Enhancement in Radiographic Testing
Nuclear Technology / Volume 72 / Number 1 / January 1986 / Pages 99-104
Technical Paper / Radioisotopes and Isotope / dx.doi.org/10.13182/NT86-A33758
On the Friction Factor for Fully Developed Turbulent Sodium Flow in Small Smooth Tubes
Nuclear Technology / Volume 72 / Number 1 / January 1986 / Pages 105-116
Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT86-A33759
A Process Inherent Ultimate Safety Boiling Water Reactor
Nuclear Technology / Volume 72 / Number 2 / February 1986 / Pages 121-134
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33735
Modeling of Boron Control During Power Transients in a Pressurized Water Reactor
Nuclear Technology / Volume 72 / Number 2 / February 1986 / Pages 135-147
Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT86-A33736
Modeling of Multiple-Component Aerosols — Sensitivities to Assumptions
Nuclear Technology / Volume 72 / Number 2 / February 1986 / Pages 148-157
Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT86-A33737
Source Term Characterization for the Maxey Flats Low-Level Radioactive Waste Disposal Site
Nuclear Technology / Volume 72 / Number 2 / February 1986 / Pages 158-177
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT86-A33738
A Melt Refining Method for Uranium-Contaminated Aluminum
Nuclear Technology / Volume 72 / Number 2 / February 1986 / Pages 178-183
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT86-A33739
Nuclear Technology / Volume 72 / Number 2 / February 1986 / Pages 184-193
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT86-A33740
Nuclear Technology / Volume 72 / Number 2 / February 1986 / Pages 194-200
Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT86-A33741
Track-Etch Neutron Radiography with a New Boron Carbide Converter
Nuclear Technology / Volume 72 / Number 2 / February 1986 / Pages 201-211
Technical Paper / Radioisotopes and Isotope / dx.doi.org/10.13182/NT86-A33742
Design of a New Counting Cell for Monitoring 85Kr in Environmental Air Samples
Nuclear Technology / Volume 72 / Number 2 / February 1986 / Pages 212-217
Technical Paper / Technique / dx.doi.org/10.13182/NT86-A33743
Nonproliferation Issue of the Pebble Bed High-Temperature Reactor
Nuclear Technology / Volume 72 / Number 2 / February 1986 / Pages 218-222
Technical Note / Fission Reactor / dx.doi.org/10.13182/NT86-A33744
Occupational Dose Reduction Experience in Ontario Hydro Nuclear Power Stations
Nuclear Technology / Volume 72 / Number 3 / March 1986 / Pages 231-245
Technical Paper / Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Nuclear Safety / dx.doi.org/10.13182/NT86-A33762
Radiation Protection Practices and Experience in French Operating Reactors
Nuclear Technology / Volume 72 / Number 3 / March 1986 / Pages 246-253
Technical Paper / Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Nuclear Safety / dx.doi.org/10.13182/NT86-A33763
Health Physics Practices and Experience at Duke Power Company
Nuclear Technology / Volume 72 / Number 3 / March 1986 / Pages 254-257
Technical Paper / Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Nuclear Safety / dx.doi.org/10.13182/NT86-A33764
Fission Product Behavior in High-Burnup Water Reactor Fuel Subjected to Slow Power Increases
Nuclear Technology / Volume 72 / Number 3 / March 1986 / Pages 258-267
Technical Paper / Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Fission Reactor / dx.doi.org/10.13182/NT86-A33765
The Reactor Containment of Standard-Design German Pressurized Water Reactors
Nuclear Technology / Volume 72 / Number 3 / March 1986 / Pages 268-290
Technical Paper / Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Fission Reactor / dx.doi.org/10.13182/NT86-A33766
Nuclear Technology / Volume 72 / Number 3 / March 1986 / Pages 291-300
Technical Paper / Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Fission Reactor / dx.doi.org/10.13182/NT86-A33767
A Dynamic Model for Pressurized Water Reactor Analysis on Microcomputers
Nuclear Technology / Volume 72 / Number 3 / March 1986 / Pages 301-311
Technical Paper / Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Fission Reactor / dx.doi.org/10.13182/NT86-A33768
Alternative Fuel Cycle Evaluation in the Federal Republic of Germany
Nuclear Technology / Volume 72 / Number 3 / March 1986 / Pages 312-320
Technical Paper / Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Fuel Cycle / dx.doi.org/10.13182/NT86-A33769
Fuel-Number Recognition by Means of Multidirectional Lighting
Nuclear Technology / Volume 72 / Number 3 / March 1986 / Pages 321-327
Technical Paper / Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Nuclear Fuel / dx.doi.org/10.13182/NT86-A33770
Model for Fuel/Cladding Chemical Interaction
Nuclear Technology / Volume 72 / Number 3 / March 1986 / Pages 328-337
Technical Paper / Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Nuclear Fuel / dx.doi.org/10.13182/NT86-A33771
Microscopic Investigation into the Irradiation Behavior of U3O8-Al Dispersion Fuel
Nuclear Technology / Volume 72 / Number 3 / March 1986 / Pages 338-344
Technical Paper / Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Nuclear Fuel / dx.doi.org/10.13182/NT86-A33772
The Use of Reconstituted Charpy Specimens to Extend R. E. Ginna Reactor Pressure Surveillance Data
Nuclear Technology / Volume 72 / Number 3 / March 1986 / Pages 345-352
Technical Paper / Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Material / dx.doi.org/10.13182/NT86-A33773
A 2D(γ,n)1H Tritiated Water Detector with 232U/228Th Source
Nuclear Technology / Volume 72 / Number 3 / March 1986 / Pages 353-358
Technical Paper / Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Analyse / dx.doi.org/10.13182/NT86-A33774
Nuclear Technology / Volume 72 / Number 3 / March 1986 / Pages 359-371
Technical Paper / Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Analyse / dx.doi.org/10.13182/NT86-A33775
Movement of Droplets in the Centrifugal Settler
Nuclear Technology / Volume 72 / Number 3 / March 1986 / Pages 372-374
Technical Note / Radiation Protection and Health Physics Practices and Experience in Operating Reactors Internationally / Chemical Processing / dx.doi.org/10.13182/NT86-A33776