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Volume 53

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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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.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 / dx.doi.org/10.13182/NT81-A32649