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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

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

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

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

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

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

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

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

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

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

 
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