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Volume 154

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Table of Contents

Nuclear Technology / Volume 154 / Number 1

April 2006

Table of Contents

Nuclear Technology / Volume 154 / Number 2

May 2006

Table of Contents

Nuclear Technology / Volume 154 / Number 3

June 2006

Investigations of Hydraulic Behavior in Spallation Target Configurations

Xu Cheng, Abdalla Batta, Nam-Il Tak

Nuclear Technology / Volume 154 / Number 1 / Pages 1-12

April 2006

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Internal Vessel Cooling Feasibility Attributed by Critical Heat Flux in Inclined Rectangular Gap

Yong H. Kim, Sung J. Kim, Kune Y. Suh, Joy L. Rempe, F. Bill Cheung, Sang B. Kim

Nuclear Technology / Volume 154 / Number 1 / Pages 13-40

April 2006

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Neutronic and Safety Aspects of a Gas-Cooled Subcritical Core for Minor Actinide Transmutation

Daniel Westlén, Janne Wallenius

Nuclear Technology / Volume 154 / Number 1 / Pages 41-51

April 2006

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Subchannel Analysis of Fuel Assemblies of European Experimental ADS

X. Cheng

Nuclear Technology / Volume 154 / Number 1 / Pages 52-68

April 2006

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Accumulation and Head-Loss Characteristics of Selected Pressurized Water Reactor LOCA-Generated Debris

Ashok K. Ghosh, Arup K. Maji, Mark T. Leonard, Dasari V. Rao, Bruce C. Letellier, Girum S. Urgessa, Scott G. Ashbaugh

Nuclear Technology / Volume 154 / Number 1 / Pages 69-84

April 2006

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Price:$30.00

Aerosol Retention Near the Tube Breach During Steam Generator Tube Rupture Sequences

Luis E. Herranz, F. J. S. Velasco, Claudia L. Del Prá

Nuclear Technology / Volume 154 / Number 1 / Pages 85-94

April 2006

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Separations and Transmutation Criteria to Improve Utilization of a Geologic Repository

Roald A. Wigeland, Theodore H. Bauer, Thomas H. Fanning, Edgar E. Morris

Nuclear Technology / Volume 154 / Number 1 / Pages 95-106

April 2006

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Results of the QUENCH-09 Experiment Compared to QUENCH-07 with Incorporation of B4C Absorber

L. Sepold, G. Schanz, M. Steinbrück, J. Stuckert, A. Miassoedov, A. Palagin, M. Veshchunov

Nuclear Technology / Volume 154 / Number 1 / Pages 107-116

April 2006

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Measurements of Delayed Fission Product Gamma-Ray Transmission Through Low-Enriched UO2 Fuel Pin Lattices in Air

T. H. Trumbull, D. R. Harris

Nuclear Technology / Volume 154 / Number 1 / Pages 117-127

April 2006

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Calculation of the Neutron Noise Induced by Shell-Mode Core-Barrel Vibrations in a 1-D, Two-Group, Two-Region Slab Reactor Model

Carl Sunde, Christophe Demazière, Imre Pázsit

Nuclear Technology / Volume 154 / Number 2 / Pages 129-141

May 2006

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A Conceptual Design Study of a Small Natural Convection Lead-Bismuth-Cooled Reactor Without Refueling for 30 Years

Yoshitaka Chikazawa, Mamoru Konomura, Tomoyasu Mizuno, Makoto Mito, Mikio Tanji

Nuclear Technology / Volume 154 / Number 2 / Pages 142-154

May 2006

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Formulation of a Single Operational Model for Risk-Informed Applications from the Decoupled Levels 1 and 2 PSA Models

Kwang-Il Ahn, Joon-Eon Yang

Nuclear Technology / Volume 154 / Number 2 / Pages 155-169

May 2006

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Mass Transfer Modeling With and Without Evaporation for Iodine Chemistry in the Case of a Severe Accident

L. Cantrel, P. March

Nuclear Technology / Volume 154 / Number 2 / Pages 170-185

May 2006

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MOX Fuel Characterization for Burnup Credit Application: Extension of Nondestructive Method Qualified for LEU Fuels

C. Riffard, H. Toubon, S. Pelletier, M. Batifol, J. M. Vidal

Nuclear Technology / Volume 154 / Number 2 / Pages 186-193

May 2006

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Modeling of Radiative Heat Transfer During a PWR Severe Accident

M. Zabiégo, F. Fichot, P. Rubiolo

Nuclear Technology / Volume 154 / Number 2 / Pages 194-214

May 2006

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The Core Characteristics of a LOCA Power Pulse in a CANDU-6 Reactor with the CANFLEX-RU Fuel

Chang Joon Jeong, Ho Chun Suk

Nuclear Technology / Volume 154 / Number 2 / Pages 215-223

May 2006

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Price:$30.00

Continuous Monitoring and Calibration of UTSG Process Sensors by Autoassociative Artificial Neural Network

Marzio Marseguerra, Enrico Zio, Fabio Marcucci

Nuclear Technology / Volume 154 / Number 2 / Pages 224-236

May 2006

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Price:$30.00
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