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Volume 57

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Number 1

Table of Contents
Authors(E. M. Dean, H. A. Larson, John M. Ryskamp, Robert A. Anderl, B. L. Broadhead, W. E. Ford III, J. L. Lucius, J. H. Marable, J. J. Wagschal, Karl Hornyik, Joseph A. Naser, D. Gauthier, C. Caput, F. Bourdeau, George C. Fullmer, Robert E. Einziger, Sharon D. Atkin, David E. Stellrecht, V. Pasupathi, Peter Weimar, Wolfgang Ernst, O. Götzmann, C. E. Johnson, S. W. Tam, P. E. Blackburn, D. C. Fee, R. L. Klueh, J. T. Dawson, G. Smith, T. F. Bott)
Materials Performance in CANDU Nuclear Steam Generators(G. F. Taylor, D. P. Dautovich)

EROS: An Experimental Breeder Reactor II Operational Safety Code

E. M. Dean, H. A. Larson

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 7-19

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT82-A16182

Sensitivity and Uncertainty Analysis of the Coupled Fast Reactivity Measurements Facility Central Flux Spectrum

John M. Ryskamp, Robert A. Anderl, B. L. Broadhead, W. E. Ford III, J. L. Lucius, J. H. Marable, J. J. Wagschal

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 20-35

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT82-A16183

RETRAN Analysis of the Turbine Trip Tests Performed at the Peach Bottom Atomic Power Station Unit 2

Karl Hornyik, Joseph A. Naser

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 36-49

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT82-A16184

Environmental Gamma-Ray Measurement Methods for French Nuclear Installation Impact Studies

D. Gauthier, C. Caput, F. Bourdeau

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 50-57

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT82-A16185

Boiling Water Reactor Cycle Extension Operation

George C. Fullmer

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 58-64

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT82-A16186

High Temperature Postirradiation Materials Performance of Spent Pressurized Water Reactor Fuel Rods Under Dry Storage Conditions

Robert E. Einziger, Sharon D. Atkin, David E. Stellrecht, V. Pasupathi

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 65-80

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A16187

Mol-7B—An 18-Pin Bundle Operating 200 Days Beyond Breach

Peter Weimar, Wolfgang Ernst

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 81-89

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A16188

Combination of Fuel-Cladding Chemical and Mechanical Interactions in Mixed Oxide Fuel Pins

O. Götzmann

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 90-103

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A16189

Fuel Chemistry Impact on Vented Fuel Pin Design

C. E. Johnson, S. W. Tam, P. E. Blackburn, D. C. Fee

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 104-113

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A16190

Heat Treatment of Cr—1 Mo Steel for Breeder Reactor Steam Generators

R. L. Klueh

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 114-124

Technical Paper / Material / dx.doi.org/10.13182/NT82-A16191

Measurement of Thermal Power Density Distributions by Fuel Pin Gamma Scanning

J. T. Dawson, G. Smith

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 125-133

Technical Paper / Technique / dx.doi.org/10.13182/NT82-A16192

An Assessment of TRAC-PD2 Refill Calculations Based on Creare Countercurrent Flow Tests

T. F. Bott

Nuclear Technology / Volume 57 / Number 1 / April 1982 / Pages 134-139

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT82-A16193

Number 2

Table of Contents
Authors(Bal Raj Sehgal, Ching-lu Lin, Edward L. Fuller, Junichi Tanji, Takashi Omori, L. E. S. Smith, R. O. Lane, P. V. Guthrie, K. Tasaka, M. Shiba, Y. Koizumi, Y. Anoda, N. Abe, Kozo Gonda, Koichiro Oka, Takeshi Nemoto, Henry H. Wong, Ertugrul Alp, W. R. Clendening, M. Tayal, Lloyd R. Jones, Lloyd B. Thomas, Sudarshan K. Loyalka, Sudarshan K. Loyalka, David J. Dixon, Mohamed A. Elmaghrabi, Ian C. Rickard, Fan Hsiung Huang, Margaret L. Hamilton, Gary L. Wire, Norberto Piccinini, Rodolfo Simonetto, Giovanni Del Tin, S. Benedek, Howard A. Larson, Charles C. Price, Robert N. Curran, John I. Sackett, Hiromi Tokoi, Hiroshi Kitaguchi, Masaaki Fujii, Katsuhiro Mizuno, Akira Ishizuka, Toyonori Kudou, Akira Ogushi, Carl M. Malbrain, Richard K. Lester, John M. Deutch)
Nuclear Reactor Kinetics and Control(Clarence E. Lee)
Simulation of Energy Systems(Archie A. Harms)
Isotopes and Radiation in Research on Soil-Plant Relationships(Alexander Van Hook)
Gravitation, Quanta and the Universe(Paul Zweifel)
Nuclear Data and Benchmarks for Reactor Shielding(Nicholas Tsoulfanidis)

A Liquid-Metal Fast Breeder Reactor Core Design with Seed Blanket Modular Assemblies

Bal Raj Sehgal, Ching-Lu Lin, Edward L. Fuller

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 149-162

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT82-A26277

Dynamic Analysis of the Condensate Feedwater System in Boiling Water Reactor Plants

Junichi Tanji, Takashi Omori

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 163-174

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT82-A26278

Experimental Modeling of Hydrogen Evolution Rates from Surfaces with Exposed Aluminum in Contact with Containment Sprays in Pressurized Water Reactor Nuclear Power Plants

L. E. S. Smith, R. O. Lane, P. V. Guthrie

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 175-178

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT82-A26279

ROSA-III Base Test Series for a Large Break Loss-of-Coolant Accident in a Boiling Water Reactor

K. Tasaka, M. Shiba, Y. Koizumi, Y. Anoda, N. Abe

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 179-191

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT82-A26280

Characteristics and Behavior of Emulsion at Nuclear Fuel Reprocessing

Kozo Gonda, Koichiro Oka, Takeshi Nemoto

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 192-202

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT82-A26281

ELESTRES: A Finite Element Fuel Model for Normal Operating Conditions

Henry H. Wong, Ertugrul Alp, W. R. Clendening,+ M. Tayal,+, Lloyd R. Jones

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 203-212

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A26282

Determination of Thermal Accommodation Coefficients of Helium, Argon, and Xenon on a Surface of Zircaloy-2 at About 25°C

Lloyd B. Thomas, Sudarshan K. Loyalka

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 213-219

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A26283

A Model for Gap Conductance in Nuclear Fuel Rods

Sudarshan K. Loyalka

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 220-227

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A26284

Cost and Other Effects of Reduced Fuel Pellet Diameters

David J. Dixon, Mohamed A. Elmaghrabi, Ian C. Rickard

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 228-233

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT82-A26285

Bend Testing for Miniature Disks

Fan Hsiung Huang, Margaret L. Hamilton, Gary L. Wire

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 234-242

Technical Paper / Material / dx.doi.org/10.13182/NT82-A26286

Gamma Treatment of Sewage Sludge with Spent Nuclear Fuel

Norberto Piccinini, Rodolfo Simonetto, Giovanni Del Tin

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 243-254

Technical Paper / Radioisotopes and Isotope / dx.doi.org/10.13182/NT82-A26287

Scaling Laws of Transient Heat and Mass Flow for Modeling the Loss-of-Coolant Accident

S. Benedek

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 255-263

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT82-A26288

Flow Measurement in Sodium and Water Using Pulsed-Neutron Activation: Part 1, Theory

Howard A. Larson, Charles C. Price, Robert N. Curran, John I. Sackett

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 264-271

Technical Paper / Analyse / dx.doi.org/10.13182/NT82-A26289

Flow Measurement in Sodium and Water Using Pulsed-Neutron Activation: Part 2, Experiment

Charles C. Price, Howard A. Larson, Robert N. Curran, John I. Sackett

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 272-284

Technical Paper / Analyse / dx.doi.org/10.13182/NT82-A26290

Application of an Ion Exchange Method for Sensitivity Improvement of an Automated Radionuclide Analysis System

Hiromi Tokoi, Hiroshi Kitaguchi, Masaaki Fujii, Katsuhiro Mizuno, Akira Ishizuka, Toyonori Kudou, Akira Ogushi

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 285-291

Technical Paper / Analyse / dx.doi.org/10.13182/NT82-A26291

Analytical Approximations for the Long-Term Decay Behavior of Spent Fuel and High-Level Waste

Carl M. Malbrain, Richard K. Lester, John M. Deutch

Nuclear Technology / Volume 57 / Number 2 / May 1982 / Pages 292-305

Technical Paper / Education / dx.doi.org/10.13182/NT82-A26292

Number 3

Table of Contents

Authors

G. B. Barton, R. F. Keough, J. J. McCown, J. A. Yount, David C. Cox, Paul Baybutt, Gert Sdouz, Sigurdur J. Dagbjartsson, Timm Preusser, Tsutomu Yokoyama, Toshiyuki Tamura, T. N. Tiegs, Tjalle T. Vandergraaf, Debbie R. M. Abry, B. A. Cheadle, C. E. Coleman, H. Licht, Bryan A. Chin, Robert J. Neuhold, Jerry L. Straalsund, Kiyoshi Sakurai

Nuclear Technology / Volume 57 / Number 3 / June 1982 / Pages 311-314

Department / dx.doi.org/10.13182/NT82-A26299

Developments in Electrochemical Oxygen Meter Probes for Use in Liquid Sodium

G. B. Barton, R. F. Keough, J. J. McCown, J. A. Yount

Nuclear Technology / Volume 57 / Number 3 / June 1982 / Pages 315-319

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT82-A26300

Limit Lines for Risk

David C. Cox, Paul Baybutt

Nuclear Technology / Volume 57 / Number 3 / June 1982 / Pages 320-330

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT82-A26301

An Analytical Study of Azimuthal Temperature Distribution in Pressurized Water Reactor Fuel Rods Under Steady-State and Blowdown Conditions

Gert Sdouz, Sigurdur J. Dagbjartsson