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Volume 154

Number 2

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 / May 2006 / Pages 129-141

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-1

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 / May 2006 / Pages 142-154

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3724

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 / May 2006 / Pages 155-169

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT06-A3725

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 / May 2006 / Pages 170-185

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT06-A3726

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 / May 2006 / Pages 186-193

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3727

Modeling of Radiative Heat Transfer During a PWR Severe Accident

M. Zabiégo, F. Fichot, P. Rubiolo

Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 194-214

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3728

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 / May 2006 / Pages 215-223

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT06-A3729

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 / May 2006 / Pages 224-236

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT06-A3730

Conditions Conducive to Forming Crystalline Uranyl Silicates in High Caustic Nuclear Waste Evaporators

Lawrence N. Oji, Keisha B. Martin, Mary E. Stallings, Martine C. Duff

Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 237-246

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT06-A3731

Thermal-Hydrologic Model Study for an Alternative Waste Package Design for Yucca Mountain Repository

D. Bahrami, G. Danko

Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 247-264

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3732

 
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