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Volume 63

Number 1

Table of Contents
Authors(R. Bruce Matthews, Richard J. Herbst, G. Kocamustafaogullari, S. H. Chan, James M. Wu, Chun-Fa Chuang, N. Scott Cannon, Gary L. Wire, John O. Barner, Richard J. Guenther, Maxwell D. Freshley, Carl E. Crouthamel, William L. Kuhn, Richard D. Peters, Scott A. Simonson, Gerhard V. P. Watzel, Ingolf Auler, Keith F. Dufrane, Michael D. Naughton, G. Romeo, Amos Notea, Yitzhak Segal, Jean-Louis Campan, Gérard Pinard-Legry, Alain J. Vignes, Guy G. Loomis, Rex W. Shumway, Yuji Enokido, Sadamu Yamanouchi, Junji Komatsu, Toshiyuki Itaki, J. V. Sandberg, J. T. Routti, Ansar Parvez, Martin Becker, Enrico Lorenzini, Pier Giacomo Sola, Marco Spiga)
Comments on“Evaluation of Volatile and Gaseous Fission Product Behavior in Water Reactor Fuel Under Normal and Severe Core Accident Conditions”(Walston Chubb)
Reply to“Comments on ‘Evaluation of Volatile and Gaseous Fission Product Behavior in Water Reactor Fuel Under Normal and Severe Core Accident Conditions’”(J. Rest)
Comments on “A Comparison of Gadolinia and Boron for Burnable Poison Applications in Pressurized Water Reactors”(Burton Rothleder)
Nuclear Fission Reactors(Nicholas Tsoulfanidis)

Uranium-Plutonium Carbide Fuel for Fast Breeder Reactors

R. Bruce Matthews, Richard J. Herbst

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 9-22

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT83-A33299

General Formulation of an HCDA Bubble Rising in a Sodium Pool and the Effect of Nonequilibrium on Fuel Transport

G. Kocamustafaogullari, S. H. Chan

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 23-39

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT83-A33300

Three-Dimensional Numerical Analysis of Natural Convection of Compacted Spent Fuel

James M. Wu, Chun-Fa Chuang

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 40-49

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33301

Controlled Biaxial Strain-Rate Testing of 20% Cold-Worked Type 316 Stainless Steel Fast Reactor Cladding

N. Scott Cannon, Gary L. Wire

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 50-62

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33302

Fuel-Cladding Mechanical Interaction in PCI-Resistant LWR Fuel Designs During Normal Operation and Power Ramping

John O. Barner, Richard J. Guenther, Maxwell D. Freshley, Carl E. Crouthamel

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 63-81

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33303

Development of a Leach Model for a Commercial Nuclear Waste Glass

William L. Kuhn, Richard D. Peters, Scott A. Simonson

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 82-89

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33304

Decommissioning of Large Nuclear Power Plants with LWRs in the Federal Republic of Germany

Gerhard V. P. Watzel, Ingolf Auler

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 90-101

Technical Paper / Economic / dx.doi.org/10.13182/NT83-A33305

Nuclear Component Wear Measurements

Keith F. Dufrane, Michael D. Naughton

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 102-109

Technical Paper / Material / dx.doi.org/10.13182/NT83-A33306

Oxidation and Radiation Buildup on Stainless Steel Components of Boiling Water Reactors

G. Romeo

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 110-120

Technical Paper / Material / dx.doi.org/10.13182/NT83-A33307

Resolving Power of Dynamic Radiation Gauges

Amos Notea, Yitzhak Segal

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 121-128

Technical Paper / Radioisotopes and Isotope / dx.doi.org/10.13182/NT83-A33308

Summary of Denting Mechanism and Kinetic Studies with Seawater

Jean-Louis Campan, Gérard Pinard-Legry, Alain J. Vignes

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 129-150

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33309

Low-Pressure Transient Flow Film Boiling in Vertically Oriented Rod Bundles

Guy G. Loomis, Rex W. Shumway

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 151-163

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33310

Development of a Shielded Ion Microprobe Analyzer (SIMA) and Its Application to Fast Reactor Fuel Elements

Yuji Enokido, Sadamu Yamanouchi, Junji Komatsu, Toshiyuki Itaki

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 164-169

Technical Paper / Technique / dx.doi.org/10.13182/NT83-A33311

Unfolding Triga Reactor Neutron Spectra from Multicomponent Activation Detector Data with LOUHI82

J. V. Sandberg, J. T. Routti

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 170-175

Technical Paper / Technique / dx.doi.org/10.13182/NT83-A33312

Relative Worth of ²³³U and ²³⁵U in Light Water Reactor Fuel Cycles

Ansar Parvez, Martin Becker

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 176-179

Technical Note / Fuel Cycle / dx.doi.org/10.13182/NT83-A33313

Radiative Heat Transfer in a Pressurized Water Reactor Fuel Bundle Under Accident Conditions

Enrico Lorenzini, Pier Giacomo Sola, Marco Spiga

Nuclear Technology / Volume 63 / Number 1 / October 1983 / Pages 180-184

Technical Note / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33314

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