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Volume 63

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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

Number 2

Table of Contents
Authors(M. Broc, J. Sannier, G. Santarini, Walter Seifritz, Kotaro Inoue, Kazuo Azekura, Katsuyuki Kawashima, Setsuo Kobayashi, Yoshio Watari, Milton H. Campbell, R. E. Tomlinson, Roy Nilson, R. F. Williams, Robert E. Brooksbank, Sr., Ray O. Sandberg, J. Novak, Ian J. Hastings, Elio Mizzan, Real J. Chenier, Arnold Friedman, Sherman Fried, Nicholas J. Susak, J. C. Sullivan, Everett L. Childs, John R. Winkel, Walter Seifritz, Michael P. Manahan, Yasuo Motoki, Mitsuo Naritomi, Mitsugu Tanaka, Gunji Nishio, Kazuichiro Hashimoto, Susumu Kitani, Werner Maschek, Margaret W. Asprey, Yutaka Kukita, Ken Namatame, Isao Takeshita, Masayoshi Shiba, Edward T. Tomlinson, C. L. Brown)
Earthquake Protection of Essential Building Equipment(George W. Housner)
Heat Transfer in Nuclear Reactor Safety(Joel Weisman)
Energy Reviews: Nuclear Power Systems—Vol. 1(Emin Yilmaz)

Experimental Studies on the Use of Liquid Lead in a Molten Salt Nuclear Reactor

M. Broc, J. Sannier, G. Santarini

Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 197-208

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT83-A33280

The Nuclear Reactor Strategy Between Fast Breeder Reactors and Advanced Pressurized Water Reactors

Walter Seifritz

Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 209-214

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT83-A33281

An Axially Heterogeneous Core Concept for Large LMFBRs and Its HCDA Behavior

Kotaro Inoue, Kazuo Azekura, Katsuyuki Kawashima, Setsuo Kobayashi, Yoshio Watari

Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 215-227

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT83-A33282

Commercial Nuclear Fuel Reprocessing Applying the SAFAR Processing Concept

Milton H. Campbell, R. E. Tomlinson, Roy Nilson, R. F. Williams

Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 228-243

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT83-A33283

Operability and Maintainability of the Barnwell Nuclear Fuel Plant: A Key Issue

Robert E. Brooksbank, Sr., Ray O. Sandberg

Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 244-253

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT83-A33284

Postirradiation Behavior of UO₂ Fuel I: Elements at 220 to 250°C in Air

J. Novak, Ian J. Hastings, Elio Mizzan, Real J. Chenier

Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 254-265

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33285

The Reduction of Neptunium(VI) by Basalt and Olivine

Nicholas J. Susak, Arnold Friedman, Sherman Fried, J. C. Sullivan

Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 266-270

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33286

Electrodecontamination of Glove-Box Materials

Everett L. Childs, John R. Winkel

Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 271-285

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33287

The Nuclear Reactor Strategy Between Light Water Reactors and Advanced Pressurized Water Reactors

Walter Seifritz

Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 286-294

Technical Paper / Economic / dx.doi.org/10.13182/NT83-A33288

A New Postirradiation Mechanical Behavior Test—The Miniaturized Disk Bend Test

Michael P. Manahan

Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 295-315

Technical Paper / Material / dx.doi.org/10.13182/NT83-A33289

Heat Removal Tests for Pressurized Water Reactor Containment Spray by Large-Scale Facility

Yasuo Motoki, Mitsuo Naritomi, Mitsugu Tanaka, Gunji Nishio, Kazuichiro Hashimoto, Susumu Kitani

Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 316-329

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33290

SIMMER-II Recriticality Analyses for a Homogeneous Core of the 300-MW(electric) Class

Werner Maschek, Margaret W. Asprey

Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 330-336

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33291

The Noncondensable Gas Effects on Loss-of-Coolant Accident Steam Condensation Loads in Boiling Water Reactor Pressure Suppression Pool

Yutaka Kukita, Ken Namatame, Isao Takeshita, Masayoshi Shiba

Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 337-346

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT83-A33292

Nuclear Criticality Safety Considerations in Design of Dry Fuel Assembly Storage Arrays

Edward T. Tomlinson, C. L. Brown

Nuclear Technology / Volume 63 / Number 2 / November 1983 / Pages 347-350

Technical Note / Nuclear Safety / dx.doi.org/10.13182/NT83-A33293

Number 3

Table of Contents
Authors(Hugo van Dam, J. Eduard Hoogenboom, Constantine P. Tzanos, Nelson A. Hanan, Achilles G. Adamantiades, J. G. Kelly, K. T. Stalker, J. P. Colletti, Samuel H. Levine, John B. Lewis, Jon L. Maienschein, Yu-Keung Sze, Joseph Alfred Gosselin, Michel Colin, Michel Coquerelle, Ian L. F. Ray, Claudio Ronchi, Clive T. Walker, Hubert Blank, Kenneth J. Hofstetter, C. G. Hitz, V. F. Baston, Anthony P. Malinauskas, L. H. Johnson, K. I. Burns, H. H. Joling, C. J. Moore, Martin A. Molecke, James A. Ruppen, Ronald B. Diegle)
Remarks on “Migration of Brine Inclusions in Salt”(I-Ming Chou)
Reply to “Remarks on ‘Migration of Brine Inclusions in Salt’”(Thomas H. Pigford)
Technical Reviewers