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Volume 123

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A Numerical Investigation of Natural Convection Heat Transfer Within Horizontal Spent-Fuel Assemblies

Robert E. Canaan, Dale E. Klein

Nuclear Technology / Volume 123 / Number 2 / Pages 193-208

August 1998

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Stresses in an Oxidized Zircaloy Cladding Under Quench Conditions: Recalculation of Single-Rod Quench Tests

Helmut Steiner, Monika Heck

Nuclear Technology / Volume 123 / Number 2 / Pages 209-221

August 1998

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A New Fuel Management Plan for The Pennsylvania State University TRIGA Reactor Including Supporting Experiments and Calculations

Patrick G. Boyle, Daniel E. Hughes, Samuel H. Levine

Nuclear Technology / Volume 123 / Number 2 / Pages 222-230

August 1998

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Pressure- and Flow-Induced Accident and Transient Analyses of a Direct-Cycle, Supercritical-Pressure, Light-Water-Cooled Fast Reactor

Kazuaki Kitoh, Seiichi Koshizuka, Yoshiaki Oka

Nuclear Technology / Volume 123 / Number 3 / Pages 233-244

September 1998

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Conceptual Design of a 50-MW Severe-Accident-Free HTR and the Related Test Program of the HTTR

Kazuhiko Kunitomi, Yukio Tachibana, Akio Saikusa, Kazuhiro Sawa, Lawrence M. Lidsky

Nuclear Technology / Volume 123 / Number 3 / Pages 245-258

September 1998

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Comparison Between MCNP and Critical Experiments - A Determination of Bias Values to Be Utilized in Licensing Calculations for High-Level Radioactive Waste Disposal

Kenneth D. Wright, James S. Tulenko, Edward T. Dugan

Nuclear Technology / Volume 123 / Number 3 / Pages 259-267

September 1998

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Use of Weapons-Grade Plutonium in Existing PWRs - Supported by German MOX Recycling Experience

Friedrich Burtak, Gerhard J. Schlosser

Nuclear Technology / Volume 123 / Number 3 / Pages 268-277

September 1998

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Determination of PWR Control Rod Position by Core Physics and Neural Network Methods

Ninos S. Garis, Imre Pázsit, Urban Sandberg, Tell Andersson

Nuclear Technology / Volume 123 / Number 3 / Pages 278-295

September 1998

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Temperature Effects on the Leaching Behavior of a High-Level Waste Glass Form

Jiawei Sheng, Shanggeng Luo, Baolong Tang

Nuclear Technology / Volume 123 / Number 3 / Pages 296-303

September 1998

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Vitrified Waste Form Performance Modeling Applied to the Treatment and Disposal of a Mixed-Waste Sludge at the Savannah River Site

A. Ryan Whited, Robert A. Fjeld, James R. Cook

Nuclear Technology / Volume 123 / Number 3 / Pages 304-319

September 1998

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Evaluation of Moderator Assemblies for Use in an Accelerator-Based Neutron Source for Boron Neutron Capture Therapy

Jeffrey E. Woollard, Thomas E. Blue, Nilendu Gupta, Reinhard A. Gahbauer

Nuclear Technology / Volume 123 / Number 3 / Pages 320-334

September 1998

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Prediction of Liquid Mixture Viscosity for Dry and Water-Saturated TBP/[italic]n[roman]-Dodecane Solutions

Shekhar Kumar, S. B. Koganti

Nuclear Technology / Volume 123 / Number 3 / Pages 335-340

September 1998

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Recovery of Fissile Materials from Wastes and Conversion of the Residual Wastes to Glass

Charles W. Forsberg, Edward C. Beahm

Nuclear Technology / Volume 123 / Number 3 / Pages 341-349

September 1998

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