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Number 1

Table of Contents
Authors (A. I. Mogilner, A. O. Skomorokhov, D. M. Shvetsov, D. W. Tedder, B. C. Finney, J. O. Blomeke, Roger G. Jarvis, Roger J. Joynes, Colleen I. Bretzlaff, B. R. Seidel, R. E. Einziger, G. D. Hudman, Glenn E. Lucas, R. M. N. Pelloux, Ming-teh Hsu, Joel Weisman, John W. Redmond, Lee A. James, Y. Ichikawa, A. Kobayashi, Y. Kitada, Kazuo Shin, Yoshitomo Uwamino, Tomonori Hyodo)
A Model for Release of Fission Gases and Volatile Fission Products from Irradiated UO2 in Steam Environment (Daniel Cubicciotti)
Turbulent Forced Convection in Channels and Bundles (Mario D. Carelli)
Innovations in Energy: The Story of Kerr-McGee (J. N. Anno)
Use of Argillaceous Materials for the Isolation of Radioactive Waste (Raymond L. Murray)

On the Problem of Noise Spectra Classification in Nuclear Power Plant Operation Diagnostics
A. I. Mogilner, A. O. Skomorokhov, D. M. Shvetsov
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
D. W. Tedder, B. C. Finney, J. O. Blomeke
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
Roger G. Jarvis, Roger J. Joynes, Colleen I. Bretzlaff
Nuclear Technology | Volume 53 | Number 1 | April 1981 | Pages 30-36
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT81-A17053
Analytical Evaluation of Ovality and Application to Fuel Elements in Experimental Breeder Reactor II Subassemblies
B. R. Seidel, R. E. Einziger, G. D. Hudman
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
Glenn E. Lucas, R. M. N. Pelloux
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
Ming-Teh Hsu, Joel Weisman, John W. Redmond+
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
Lee A. James
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
Y. Ichikawa, A. Kobayashi, Y. Kitada
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
Kazuo Shin, Yoshitomo Uwamino, Tomonori Hyodo
Nuclear Technology | Volume 53 | Number 1 | April 1981 | Pages 78-85
Technical Paper | Analyse | doi.org/10.13182/NT81-A17059

Number 2

Table of Contents
Authors (M. Levenson, F.Rahn, D. O. Campbell, A. P. Malinauskas, W. R. Stratton, H. A. Morewitz, G. W. Parker, G. E. Creek, H. Bunz, W. Schikarski, W. Schöck, R. R. Smith, Z. T. Mendoza, C. A. Stevens, R. L. Ritzman, R. K. Hilliard, A. K. Postma, M. A. Feraday, Emile Vanden Bemd, R. L. Nelson, N. Parkinson, W. C. L. Kent, Dennis L. Berry, T. G. Broughton, P. S. Walsh, Yurii Mikhailovich Karatsuba, G. S. Lellouche, Walter E. Clark, W. B. Howerton, J. C. Mailen, R. Kolowith, D. V. Archer, F.E. Holt, W. C. Miller, J. J. McCown, E. B. J. Kleiss, H.van Dam)
A Perspective (Milton Levenson)
Applied Hydraulic Transients (Robert S. Wick)
Fermi-I: New Age for Nuclear Power (Lloyd R. Zumwalt)
Kinetics of lon-Molecule Reactions (R. J. Woods)
Boiling Phenomena (Robert S. Wick)

Realistic Estimates of the Consequences of Nuclear Accidents
M. Levenson, F. Rahn
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
D. O. Campbell, A. P. Malinauskas, W. R. Stratton
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
H. A. Morewitz
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
Impact of Secondary Effects on the Reduction of Fission Product Source Terms in Class IX Reactor Accidents
G. W. Parker, G. E. Creek
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
R. R. Smith
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
Z. T. Mendoza, C. A. Stevens, R. L. Ritzman
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
R. K. Hilliard, A. K. Postma
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
M. A. Feraday
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
Emile Vanden Bemden
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
R. L. Nelson, N. Parkinson, W. C. L. Kent
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
Dennis L. Berry
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
T. G. Broughton, P. S. Walsh
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
On Evaluation of the Statistical Error in Measuring the Reactor Period and Reactivity in Case of a Drift-Type Disturbance
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
Walter E. Clark, W. B. Howerton, J. C. Mailen
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
Development of In-Core Gas Release Devices for Fast Flux Test Facility Fuel Failure Monitoring System Testing
R. Kolowith, D. V. Archer, F. E. Holt, W. C. Miller, J. J. McCown
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 (A. A. Harms, M. Heindler, William L. MacCready, John A. Wethington, Jr., Glen A. Watford, John A. Wethington, Jr., Samuel H. Levine, Joel Weisman,Roy Eckart, William L. MacCready, John A. Wethington, Jr., Fred J. Hurst, Mohamed S. El-Genk, Richard L. Moore, R. C. Erdmann, F. L. Leverenz, Jr. G. S. Lellouche, S. Benedek, L. E. S. Smith, R. O. Lane, W. Alexander Van Hook, V. A. Kazakov, A. S. Pokrovsky, A. V. Smirnov, S. Shann, D. R. Olander)
Further Comments On“the Uncertainty in Accident Consequences Calculated by Large Codes Due to Uncertainties in Input” (Steven M. Baker)
Reply to“Further Comments on ‘the Uncertainty in Accident Consequences Calculated by Large Codes Due to Uncertainties in Input’” (D. H. Nguyen)
Studies in Heat Transfer, A Festschrift for E.R.G. Eckert (Samuel H. Levine)
The Particle Play (Mark A. Samuel)
Fast Pulsed and Burst Reactors (Noel R. Corngold)
Computer Techniques in Radiation Transport and Dosimetry (John W. Poston)
Commonsense in Nuclear Energy (Harry W. Parker)
“Realistic Estimates of the Consequences of Nuclear Accidents,”

Theory and Application of the Nuclear Fuel Trajectory Concept
A. A. Harms, M. Heindler
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
William L. MacCready, John A. Wethington, Jr.
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
Glen A. Watford, John A. Wethington, Jr.
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
Samuel H. Levine
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
Joel Weisman, Roy Eckart
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
William L. MacCready, John A. Wethington, Jr., Fred J. Hurst
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
Transient Debris Freezing and Potential Wall Melting During a Severe Reactivity Initiated Accident Experiment
Mohamed S. El-Genk, Richard L. Moore
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
R. C. Erdmann, F. L. Leverenz, Jr., G. S. Lellouche
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
Analysis of Pressurized Water Reactor Primary Circuit Processes and Fuel Rod Heatup in the Case of Separated Coolant
S. Benedek
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
Experimental Modeling of Hydrogen Evolution Rates from Surfaces with Exposed Zinc Metal or Zinc Primer Coating in Contact with Containment Sprays in PWR Nuclear Power Plants
L. E. S. Smith, R. O. Lane, W. Alexander Van Hook
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
V. A. Kazakov, A. S. Pokrovsky, A. V. Smirnov
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
S. Shann, D. R. Olander
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

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