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Volume 86

Number 3

Present Status of Fast Breeder Reactor Development in Japan

Sadamu Sawai, Yonesuke Iwakoshi

Nuclear Technology / Volume 86 / Number 3 / September 1989 / Pages 219-232

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34290

Codes and Standards for Fast Breeder Reactor Components—A European Point of View

Roland L. Roche, C. H. A. Townley, Kurt Vinzens, H. Laue, Franco Corsi, M. De Bacci

Nuclear Technology / Volume 86 / Number 3 / September 1989 / Pages 233-238

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34291

Defective Fuel Rod Detection in Operating Pressurized Water Reactors During Periods of Continuously Decreasing Fuel Rod Integrity Levels

Harald Zänker

Nuclear Technology / Volume 86 / Number 3 / September 1989 / Pages 239-247

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34292

Low-Enriched Uranium Conversion/Power Upgrade of The Ohio State University Research Reactor

Tunc Aldemir, Joseph W. Talnagi,*, Don W. Miller

Nuclear Technology / Volume 86 / Number 3 / September 1989 / Pages 248-263

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT89-A34293

Fast Flux Test Facility Fuel Handling Experience—November 1979 to August 1988

Delwin M. Romrell, Don M. Art, Richard D. Redekopp, James B. Waldo, Jerry L. Marshall

Nuclear Technology / Volume 86 / Number 3 / September 1989 / Pages 264-274

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT89-A34294

An Improvement in the Use of Plutonium in Pressurized Water Reactors: The Subassembly Mixed-Oxide Fuel Management Concept

Corinne Bangil, Gérard Gambier, Michel Soldevila

Nuclear Technology / Volume 86 / Number 3 / September 1989 / Pages 275-281

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT89-A34295

Equilibrium Time and Criticality Considerations in Uranium Enrichment by the Chemical-Exchange Process

Yasuhiko Fujii, Makoto Okamoto, Hiroyuki Kadotani, Hidetake Kakihana

Nuclear Technology / Volume 86 / Number 3 / September 1989 / Pages 282-288

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT89-A34296

Increased-Discharge-Burnup Method for Multicycle Reload Design

Hyong Chol Kim, Ming-Yuan Hsiao, Samuel H. Levine

Nuclear Technology / Volume 86 / Number 3 / September 1989 / Pages 289-304

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT89-A34297

Long-Term Isolation of High-Level Radioactive Waste in Salt Repositories Containing Brine

Donald G. Schweitzer, Cesar A. Sastre

Nuclear Technology / Volume 86 / Number 3 / September 1989 / Pages 305-312

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT89-A34298