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Volume 152

Number 1

Influence of the Pipe Diameter on the Structure of the Gas-Liquid Interface in a Vertical Two-Phase Pipe Flow

H.-M. Prasser, M. Beyer, A. Böttger, H. Carl, D. Lucas, A. Schaffrath, P. Schütz, F.-P. Weiss, J. Zschau

Nuclear Technology / Volume 152 / Number 1 / October 2005 / Pages 3-22

Technical Paper / Nuclear Reactor Thermal Hydraulics

Two-Phase Void Drift Phenomena in a 2 × 3 Rod Bundle: Flow Redistribution Data and Their Analysis

Michio Sadatomi, Akimaro Kawahara, Tsukasa Kuno, Keiko Kano

Nuclear Technology / Volume 152 / Number 1 / October 2005 / Pages 23-37

Technical Paper / Nuclear Reactor Thermal Hydraulics

Suitability of Drift-Flux Models, Void-Fraction Evolution, and 3-D Flow Pattern Visualization During Stationary and Transient Flashing Flow in a Vertical Pipe

Annalisa Manera, Horst-Michael Prasser, Tim H. J. J. van der Hagen

Nuclear Technology / Volume 152 / Number 1 / October 2005 / Pages 38-53

Technical Paper / Nuclear Reactor Thermal Hydraulics

Theoretical Foundation for an Electromagnetic Two-Phase Flowmetry

Yeh-Chan Ahn, Byung Do Oh, Moo Hwan Kim

Nuclear Technology / Volume 152 / Number 1 / October 2005 / Pages 54-70

Technical Paper / Nuclear Reactor Thermal Hydraulics

Investigation of the Noncondensable Effect and the Operational Modes of the Passive Condenser System

Seungmin Oh, Shripad T. Revankar

Nuclear Technology / Volume 152 / Number 1 / October 2005 / Pages 71-86

Technical Paper / Nuclear Reactor Thermal Hydraulics

Lookup Tables for Predicting CHF and Film-Boiling Heat Transfer: Past, Present, and Future

D. C. Groeneveld, L. K. H. Leung, Y. Guo, A. Vasic, M. El Nakla, S. W. Peng, J. Yang, S. C. Cheng

Nuclear Technology / Volume 152 / Number 1 / October 2005 / Pages 87-104

Technical Paper / Nuclear Reactor Thermal Hydraulics

Application of the Post-Boiling-Transition Standard to Licensing Analysis

Shinya Mizokami, Hideya Kitamura, Yoshiro Kudo, Seiichi Komura, Yoshifumi Nagata, Shinichi Morooka

Nuclear Technology / Volume 152 / Number 1 / October 2005 / Pages 105-117

Technical Paper / Nuclear Reactor Thermal Hydraulics

Life Estimation of PWR Steam Generator U-Tubes Subjected to Foreign Object-Induced Fretting Wear

Jong Chull Jo, Myung Jo Jhung, Woong Sik Kim, Hho Jung Kim

Nuclear Technology / Volume 152 / Number 1 / October 2005 / Pages 118-128

Technical Paper / Nuclear Reactor Thermal Hydraulics

A Three-Dimensional Two-Fluid Modeling of Stratified Flow with Condensation for Pressurized Thermal Shock Investigations

W. Yao, D. Bestion, P. Coste, M. Boucker

Nuclear Technology / Volume 152 / Number 1 / October 2005 / Pages 129-142

Technical Paper / Nuclear Reactor Thermal Hydraulics

 
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