Number 1
- Table of Contents
- Authors
- A Model for Release of Fission Gases and Volatile Fission Products from Irradiated UO2 in Steam Environment
- Turbulent Forced Convection in Channels and Bundles
- Innovations in Energy: The Story of Kerr-McGee
- Use of Argillaceous Materials for the Isolation of Radioactive Waste
On the Problem of Noise Spectra Classification in Nuclear Power Plant Operation Diagnostics
Nuclear Technology | Volume 53 | Number 1 | April 1981 | Pages 8-18
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A17051
Chemical Processing Facilities for Partitioning Actinides from Nuclear Fuel Cycle Waste Mixtures
Nuclear Technology | Volume 53 | Number 1 | April 1981 | Pages 19-29
Technical Paper | Chemical Processing | doi.org/10.13182/NT81-A17052
A Mathematical Model of an Automatic Assembler to Stack Fuel Pellets
Nuclear Technology | Volume 53 | Number 1 | April 1981 | Pages 30-36
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A17053
Nuclear Technology | Volume 53 | Number 1 | April 1981 | Pages 37-45
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A17054
Some Observations on Time-Hardening and Strain-Hardening Rules for Creep in Zircaloy-2
Nuclear Technology | Volume 53 | Number 1 | April 1981 | Pages 46-57
Technical Paper | Material | doi.org/10.13182/NT81-A17055
An Evaluation of Time-Dependent Loading Analysis on a Piping Network Using RELAP4/REPIPE
Nuclear Technology | Volume 53 | Number 1 | April 1981 | Pages 58-63
Technical Paper | Material | doi.org/10.13182/NT81-A17056
Effect of Fast Neutron Irradiation on Fatigue-Crack Growth Behavior of Three Nickel-Base Alloys
Nuclear Technology | Volume 53 | Number 1 | April 1981 | Pages 64-68
Technical Paper | Material | doi.org/10.13182/NT81-A17057
Real-Time Simulation of Gamma Exposure Rate by Puff Model
Nuclear Technology | Volume 53 | Number 1 | April 1981 | Pages 69-77
Technical Paper | Radiation Biology and Environment | doi.org/10.13182/NT81-A17058
Propagation of Errors from Response Functions to Unfolded Spectrum
Nuclear Technology | Volume 53 | Number 1 | April 1981 | Pages 78-85
Technical Paper | Analyse | doi.org/10.13182/NT81-A17059
Number 2
Realistic Estimates of the Consequences of Nuclear Accidents
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 99-110
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Safety | doi.org/10.13182/NT81-A32614
The Chemical Behavior of Fission Product Iodine in Light Water Reactor Accidents
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 111-119
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Safety | doi.org/10.13182/NT81-A32615
Fission Product and Aerosol Behavior Following Degraded Core Accidents
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 120-134
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Safety | doi.org/10.13182/NT81-A32616
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 135-140
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Safety | doi.org/10.13182/NT81-A32617
The Role of Aerosol Behavior in Light Water Reactor Core Melt Accidents
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 141-146
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Safety | doi.org/10.13182/NT81-A32618
Radiological Consequences of BORAX/SPERT/SNAPTRAN Experiments
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 147-154
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Safety | doi.org/10.13182/NT81-A32619
Radiation Releases from the SL-1 Accident
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 155-162
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Safety | doi.org/10.13182/NT81-A32620
Large-Scale Fission Product Containment Tests
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 163-175
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Safety | doi.org/10.13182/NT81-A32621
Remote Fabrication of (Th,233U)O2 Pellet-Type Fuels for CANDU Reactors
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 176-185
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Fuel | doi.org/10.13182/NT81-A32622
Fabrication of Plutonium-Enriched Fuel at Belgonucleaire
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 186-195
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Fuel | doi.org/10.13182/NT81-A32623
U.K. Development Toward Remote Fabrication of Breeder Reactor Fuel
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 196-203
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Fuel | doi.org/10.13182/NT81-A32624
Analysis of Fire Barriers Within Nuclear Power Plants
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 204-216
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Fission Reactor | doi.org/10.13182/NT81-A32625
A Real-Time Method for Analyzing Nuclear Power Plant Transients
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 217-225
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Fission Reactor | doi.org/10.13182/NT81-A32626
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 226-230
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Fission Reactor | doi.org/10.13182/NT81-A32627
WASH-1400: A Comparison of Experience and Prediction
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 231-234
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Safety | doi.org/10.13182/NT81-A32628
The Removal of Trace Contaminants from Recycle Nitric Acid
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 235-240
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Chemical Processing | doi.org/10.13182/NT81-A32629
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 241-249
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Nuclear Fuel | doi.org/10.13182/NT81-A32630
A Twin Self-Powered Neutron Detector for Steam Velocity Determination in a Boiling Water Reactor
Nuclear Technology | Volume 53 | Number 2 | May 1981 | Pages 250-256
Technical Paper | Realistic Estimates of the Consequences of Nuclear Accident / Radioisotope and Isotope | doi.org/10.13182/NT81-A32631
Number 3
- Table of Contents
- Authors
- Further Comments On“the Uncertainty in Accident Consequences Calculated by Large Codes Due to Uncertainties in Input”
- Reply to“Further Comments on ‘the Uncertainty in Accident Consequences Calculated by Large Codes Due to Uncertainties in Input’”
- Studies in Heat Transfer, A Festschrift for E.R.G. Eckert
- The Particle Play
- Fast Pulsed and Burst Reactors
- Computer Techniques in Radiation Transport and Dosimetry
- Commonsense in Nuclear Energy
- “Realistic Estimates of the Consequences of Nuclear Accidents,”
Theory and Application of the Nuclear Fuel Trajectory Concept
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 267-279
Technical Paper | Nuclear Fuel Cycle Education Module / Education | doi.org/10.13182/NT81-A32638
Solvent Extraction and Ion Exchange in the Nuclear Fuel Industry
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 280-294
Technical Paper | Nuclear Fuel Cycle Education Module / Education | doi.org/10.13182/NT81-A32639
Radiological Hazards of Uranium Mill Tailings Piles
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 295-302
Technical Paper | Nuclear Fuel Cycle Education Module / Education | doi.org/10.13182/NT81-A32640
In-Core Fuel Management Educational Module
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 303-325
Technical Paper | Nuclear Fuel Cycle Education Module / Education | doi.org/10.13182/NT81-A32641
Basic Elements of Light Water Reactor Fuel Rod Design
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 326-343
Technical Paper | Nuclear Fuel Cycle Education Module / Education | doi.org/10.13182/NT81-A32642
Uranium Extraction from Florida Phosphates
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 344-353
Technical Paper | Nuclear Fuel Cycle Education Module / Education | doi.org/10.13182/NT81-A32643
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 354-373
Technical Paper | Nuclear Fuel Cycle Education Module / Nuclear Safety | doi.org/10.13182/NT81-A32644
WASH-1400: Quantifying the Uncertainties
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 374-380
Technical Paper | Nuclear Fuel Cycle Education Module / Nuclear Safety | doi.org/10.13182/NT81-A32645
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 381-387
Technical Paper | Nuclear Fuel Cycle Education Module / Nuclear Safety | doi.org/10.13182/NT81-A32646
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 388-391
Technical Paper | Nuclear Fuel Cycle Education Module / Material | doi.org/10.13182/NT81-A32647
Strengthening and Void Formation in the Mo-Zr-B Alloy Under Neutron Irradiation
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 392-406
Technical Paper | Nuclear Fuel Cycle Education Module / Material | doi.org/10.13182/NT81-A32648
Correlation of Failure Times for Iodine Stress Corrosion Cracking of Zircaloy
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 407-409
Technical Note | Nuclear Fuel Cycle Education Module / Nuclear Fuel | doi.org/10.13182/NT81-A32649