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Volume 63

Number 3

Physics of a Gaseous Core Reactor

Hugo Van Dam, J. Eduard Hoogenboom

Nuclear Technology / Volume 63 / Number 3 / December 1983 / Pages 359-368

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT83-A33265

An Assessment of the Core Degradation Frequency in a Typical Large LMFBR Design for Internal Accident Initiators—A Comparison with PWR Predictions

Constantine P. Tzanos, Nelson A. Hanan, Achilles G. Adamantiades

Nuclear Technology / Volume 63 / Number 3 / December 1983 / Pages 369-396

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT83-A33266

Performance Characteristics of the Annular Core Research Reactor Fuel Motion Detection System

J. G. Kelly, K. T. Stalker

Nuclear Technology / Volume 63 / Number 3 / December 1983 / Pages 397-414

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT83-A33267

Iterative Solution to the Optimal Poison Management Problem in Pressurized Water Reactors

J. P. Colletti, Samuel H. Levine, John B. Lewis

Nuclear Technology / Volume 63 / Number 3 / December 1983 / Pages 415-425

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT83-A33268

The Possibility for Spark-Initiated Explosion in Mixtures of Uranium Hexafluoride and Deuterium

Jon L. Maienschein

Nuclear Technology / Volume 63 / Number 3 / December 1983 / Pages 426-430

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT83-A33269

Oxidation of Pu(III) by Nitric Acid in Tri-n-Butyl Phosphate Solutions. Part II. Chemical Methods for the Suppression of Oxidation to Improve Plutonium Separation in Contactor Operation

Yu-Keung Sze, Joseph Alfred Gosselin

Nuclear Technology / Volume 63 / Number 3 / December 1983 / Pages 431-441

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT83-A33270

The Sodium-Bonding Pin Concept for Advanced Fuels Part I: Swelling of Carbide Fuel up to 12% Burnup

Michel Colin, Michel Coquerelle, Ian L. F. Ray, Claudio Ronchi, Clive T. Walker, Hubert Blank

Nuclear Technology / Volume 63 / Number 3 / December 1983 / Pages 442-460

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT83-A33271

Radionuclide Analyses Taken During Primary Coolant Decontamination at Three Mile Island Indicate General Circulation

Kenneth J. Hofstetter, C. G. Hitz, V. F. Baston, Anthony P. Malinauskas

Nuclear Technology / Volume 63 / Number 3 / December 1983 / Pages 461-469

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33272

Leaching of 137Cs, 134Cs, and 129I from Irradiated UO2 Fuel

L. H. Johnson, K. I. Burns, H. H. Joling, C. J. Moore

Nuclear Technology / Volume 63 / Number 3 / December 1983 / Pages 470-475

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33273

Materials for High-Level Waste Canister/Overpacks in Salt Formations

Martin A. Molecke, James A. Ruppen, Ronald B. Diegle

Nuclear Technology / Volume 63 / Number 3 / December 1983 / Pages 476-506

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT83-A33274