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Volume 69

Number 2

Table of Contents
Authors(Edward T. Dugan, Nils J. Diaz, Edward E. Carroll, Jr., H. M. Forehand, E. Dow Whitney, Dae Joon Kim, Dennis S. Tucker, Calvin C. Oliver, Edward T. Dugan, Hans S. Häggblom, Werner Faubel, Sameh A. Ali, R. Kohli, D. Stahl, V. Pasupathi, A. B. Johnson, Jr., E. R. Gilbert, Richard W. Smith, Gary S. Was, Yasunori Bessho, Sadao Uchikawa, Clarence E. Lee, Joe W. Durkee, H. Mogard, H. Knaab, U. Bergenlid, G. Lysell)
Preface: Gaseous Core Reactors(Nils J. Diaz)

Gas Core Reactor Neutronics —Theoretical Modeling and Experimental Verification

Edward T. Dugan, Nils J. Diaz, Edward E. Carroll, Jr., H. M. Forehand

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 134-153

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33625

A Study of Corrosion-Resistant Materials for Pulsed Gaseous Core Nuclear Systems

E. Dow Whitney, Dae Joon Kim, Dennis S. Tucker+

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 154-160

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33626

Thermophysical Properties of UF₆-He Mixtures Relevant to Circulating Gas Core Reactor Systems

Calvin C. Oliver, Edward T. Dugan

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 161-169

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33627

Transfer of Molecular Fission Products Between a Gas and a Surface, with Application to Iodine Retention in a Granular Bed

Hans S. Häggblom

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 170-177

Nuclear Safety / dx.doi.org/10.13182/NT85-A33628

Decontamination of Carbonate Containing Process Streams in Nuclear Fuel Reprocessing by Ion Exchange Chromatography

Werner Faubel, Sameh A. AL

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 178-185

Chemical Processing / dx.doi.org/10.13182/NT85-A33629

The Behavior of Breached Boiling Water Reactor Fuel Rods on Long-Term Exposure to Air and Argon at 598 K

R. Kohli, D. Stahl, V. Pasupathi, A. B. Johnson, Jr., E. R. Gilbert

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 186-197

Nuclear Fuel / dx.doi.org/10.13182/NT85-A33630

FCODE-BETA/SS: A Fuel Performance Code for Stainless Steel Clad Pressurized Water Reactor Fuel

Richard W. Smith, Gary S. Was

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 198-209

Nuclear Fuel / dx.doi.org/10.13182/NT85-A33631

Subchannel Analysis Program for Boiling Water Reactor Fuel Bundles Based on Five Conservation Equations of Two-Phase Flow

Yasunori Bessho, Sadao Uchikawa

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 210-217

Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33632

Multiregion Concentration Diffusion Coefficient Determination Using Davidon’s Variable Metric Method

Clarence E. Lee, Joe W. Durkee

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 218-235

Analyse / dx.doi.org/10.13182/NT85-A33633

The International DEMO-RAMP-II Project at Studsvik

H. Mogard, H. Knaab, U. Bergenlid, G. Lysell

Nuclear Technology / Volume 69 / Number 2 / May 1985 / Pages 236-242

Technical Note / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33634

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