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Volume 127

Number 2

A MELCOR-Based Model to Calculate Vapor Natural Circulation in Pressurized Water Reactor High-Pressure Severe Accidents

Francisco Martín-Fuertes Hernández-Sonseca

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 141-150

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT99-A2990

Modeling of the Rim Effect on Thermal Behavior of High-Burnup UO2 Fuel

Byung-Ho Lee, Yang-Hyun Koo, Dong-Seong Sohn

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 151-159

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT99-A2991

A Condensation Experiment in the Presence of Noncondensables in a Vertical Tube of a Passive Containment Cooling System and Its Assessment with RELAP5/MOD3.2

Hyun Sik Park, Hee Cheon No

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 160-169

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT99-A2992

Core Damage Severity Evaluation for Pressurized Water Reactors by Use of Fuzzy Logic Algorithms

Anastasios Mironidis, Leon Lidofsky, George Grochowski, Lefteris Tsoukalas

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 170-185

Technical Paper / Reactor Operations and Control / dx.doi.org/10.13182/NT99-A2993

Conceivable Limits for Thermal Reactor Spent-Fuel Recycling

David R. Kingdon, Vladimir A. Khotylev, Archie A. Harms, J. Eduard Hoogenboom

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 186-198

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT99-A2994

Matrix Diffusion of Simple Cations, Anions, and Neutral Species in Fractured Crystalline Rocks

Haruo Sato

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 199-211

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT127-199

Evaluation of the Effect of Temperature on Potassium Clinoptilolite Ion Exchange

David A. White, Andreas Nattkemper, Radu Ratautiu

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 212-217

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT99-A2996

Design of the European Spallation Source Liquid-Metal Target Using Computational Fluid Dynamics

Trevor V. Dury, Brian L. Smith, Günter S. Bauer

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 218-232

Technical Paper / Accelerators / dx.doi.org/10.13182/NT99-A2997

An Electrocatalyzed Process for Leaching of Plutonium from Active Gauntlets and Subsequent Separation by Solvent Extraction

K. Venugopal Chetty, P. M. Mapara, A. G. Godbole, Rajendra Swarup

Nuclear Technology / Volume 127 / Number 2 / August 1999 / Pages 233-237

Technical Note / Reprocessing / dx.doi.org/10.13182/NT99-A2998