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Volume 145

Number 2

Determination of Limit Cycles Using Both the Slope of Correlation Integral and Dominant Lyapunov Methods

Rogelio Castillo, Gustavo Alonso, Javier C. Palacios

Nuclear Technology / Volume 145 / Number 2 / February 2004 / Pages 139-149

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT04-A3465

Dynamic Comparison of Three- and Four-Equation Reactor Core Models in a Full-Scope Power Plant Training Simulator

Gilberto Espinosa-Paredes, Jose Alvarez-Ramirez, Alejandro Nuñez-Carrera, Alfonso Garcia-Gutierrez, Elizabeth Jeannette Martinez-Mendez

Nuclear Technology / Volume 145 / Number 2 / February 2004 / Pages 150-162

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3466

Void Fraction and Critical Power Assessment of CORETRAN-01/VIPRE-02

Yacine Aounallah

Nuclear Technology / Volume 145 / Number 2 / February 2004 / Pages 163-176

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3467

Application of Wavelet Noise-Reduction Technique to Water-Level Controller

Gee Yong Park, Jinho Park, Poong Hyun Seong

Nuclear Technology / Volume 145 / Number 2 / February 2004 / Pages 177-188

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT04-A3468

A Personal Computer-Based Simulation-and-Control-Integrated Platform for 10-MW High-Temperature Gas-Cooled Reactor

Lei Shi, Haibin Liu, Xiaojing Yang, Zuying Gao, Yujie Dong, Zuoyi Zhang

Nuclear Technology / Volume 145 / Number 2 / February 2004 / Pages 189-203

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT04-A3469

Evaluation of 235U Isotopic Dilution with the Addition of Depleted Uranium to Supernatant Liquid Waste

Lawrence N. Oji, David T. Hobbs, Paul D. d'Entremont

Nuclear Technology / Volume 145 / Number 2 / February 2004 / Pages 204-214

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT04-A3470

Evaluation of Uranium Coprecipitation with Sodium Aluminosilicate Phases

Lawrence N. Oji, Adrienne L. Williams

Nuclear Technology / Volume 145 / Number 2 / February 2004 / Pages 215-229

Technical Paper / Reprocessing / dx.doi.org/10.13182/NT04-A3471

Development of a Fast Breeder Reactor Fuel Bundle Deformation Analysis Code - BAMBOO: Development of a Pin Dispersion Model and Verification by the Out-of-Pile Compression Test

Tomoyuki Uwaba, Masahiro Ito, Shigeharu Ukai

Nuclear Technology / Volume 145 / Number 2 / February 2004 / Pages 230-237

Technical Note / Materials for Nuclear Systems / dx.doi.org/10.13182/NT04-A3472

 
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