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ANS > Publications > Journals > Nuclear Technology > Volume 152
Number 1  ·  Number 2  ·  Number 3
Number 1 · October 2005
Table of Contents
Foreword (Soon Heung Chang, Won-Pil Baek, Joy Rempe)
Influence of the Pipe Diameter on the Structure of the Gas-Liquid Interface in a Vertical Two-Phase Pipe Flow
Volume 152 · Number 1 · October 2005 · Pages 3-22
Technical Paper · Nuclear Reactor Thermal Hydraulics

H.-M. Prasser, M. Beyer, A. Böttger, H. Carl, D. Lucas, A. Schaffrath, P. Schütz, F.-P. Weiss, J. Zschau
Two-Phase Void Drift Phenomena in a 2 × 3 Rod Bundle: Flow Redistribution Data and Their Analysis
Volume 152 · Number 1 · October 2005 · Pages 23-37
Technical Paper · Nuclear Reactor Thermal Hydraulics

Michio Sadatomi, Akimaro Kawahara, Tsukasa Kuno, Keiko Kano
Suitability of Drift-Flux Models, Void-Fraction Evolution, and 3-D Flow Pattern Visualization During Stationary and Transient Flashing Flow in a Vertical Pipe
Volume 152 · Number 1 · October 2005 · Pages 38-53
Technical Paper · Nuclear Reactor Thermal Hydraulics

Annalisa Manera, Horst-Michael Prasser, Tim H. J. J. van der Hagen
Theoretical Foundation for an Electromagnetic Two-Phase Flowmetry
Volume 152 · Number 1 · October 2005 · Pages 54-70
Technical Paper · Nuclear Reactor Thermal Hydraulics

Yeh-Chan Ahn, Byung Do Oh, Moo Hwan Kim
Investigation of the Noncondensable Effect and the Operational Modes of the Passive Condenser System
Volume 152 · Number 1 · October 2005 · Pages 71-86
Technical Paper · Nuclear Reactor Thermal Hydraulics

Seungmin Oh, Shripad T. Revankar
Lookup Tables for Predicting CHF and Film-Boiling Heat Transfer: Past, Present, and Future
Volume 152 · Number 1 · October 2005 · Pages 87-104
Technical Paper · Nuclear Reactor Thermal Hydraulics

D. C. Groeneveld, L. K. H. Leung, Y. Guo, A. Vasic, M. El Nakla, S. W. Peng, J. Yang, S. C. Cheng
Application of the Post-Boiling-Transition Standard to Licensing Analysis
Volume 152 · Number 1 · October 2005 · Pages 105-117
Technical Paper · Nuclear Reactor Thermal Hydraulics

Shinya Mizokami, Hideya Kitamura, Yoshiro Kudo, Seiichi Komura, Yoshifumi Nagata, Shinichi Morooka
Life Estimation of PWR Steam Generator U-Tubes Subjected to Foreign Object-Induced Fretting Wear
Volume 152 · Number 1 · October 2005 · Pages 118-128
Technical Paper · Nuclear Reactor Thermal Hydraulics

Jong Chull Jo, Myung Jo Jhung, Woong Sik Kim, Hho Jung Kim
A Three-Dimensional Two-Fluid Modeling of Stratified Flow with Condensation for Pressurized Thermal Shock Investigations
Volume 152 · Number 1 · October 2005 · Pages 129-142
Technical Paper · Nuclear Reactor Thermal Hydraulics

W. Yao, D. Bestion, P. Coste, M. Boucker
Number 2 · November 2005
Table of Contents
Foreword (Soon Heung Chang, Won-Pil Baek, Joy Rempe)
Limiting Factors for External Reactor Vessel Cooling
Volume 152 · Number 2 · November 2005 · Pages 145-161
Technical Paper · Nuclear Reactor Thermal Hydraulics

F. B. Cheung
Critical Heat Flux Experiments on the Reactor Vessel Wall Using 2-D Slice Test Section
Volume 152 · Number 2 · November 2005 · Pages 162-169
Technical Paper · Nuclear Reactor Thermal Hydraulics

Yong Hoon Jeong, Soon Heung Chang, Won-Pil Baek
Development of an Enhanced Core Catcher for Improving In-Vessel Retention Margins
Volume 152 · Number 2 · November 2005 · Pages 170-182
Technical Paper · Nuclear Reactor Thermal Hydraulics

J. L. Rempe, K. G. Condie, D. L. Knudson, K. Y. Suh, F. B. Cheung, S. B. Kim
KAERI Integral Effect Test Program and the ATLAS Design
Volume 152 · Number 2 · November 2005 · Pages 183-195
Technical Paper · Nuclear Reactor Thermal Hydraulics

Won-Pil Baek, Chul-Hwa Song, Byong-Jo Yun, Tae-Soon Kwon, Sang-Ki Moon, Sung-Jae Lee
Evolution of Design Methodologies for Next Generation of Reactor Pressure Vessels and Extensive Role of Thermal-Hydraulic Numerical Tools
Volume 152 · Number 2 · November 2005 · Pages 196-209
Technical Paper · Nuclear Reactor Thermal Hydraulics

Serge Bellet, Nicolas Goreaud, Norbert Nicaise
Experimental Study on Flow Optimization in Upper Plenum of Reactor Vessel for a Compact Sodium-Cooled Fast Reactor
Volume 152 · Number 2 · November 2005 · Pages 210-222
Technical Paper · Nuclear Reactor Thermal Hydraulics

Nobuyuki Kimura, Kenji Hayashi, Hideki Kamide, Masami Itoh, Tadashi Sekine
Computational Study of Thermal Striping in an Upper Plenum of Kalimer
Volume 152 · Number 2 · November 2005 · Pages 223-238
Technical Paper · Nuclear Reactor Thermal Hydraulics

Seok-Ki Choi, Myung-Hwan Wi, Won-Dae Jeon, Seong-O Kim
New Challenges in Computational Thermal Hydraulics
Volume 152 · Number 2 · November 2005 · Pages 239-251
Technical Paper · Nuclear Reactor Thermal Hydraulics

George Yadigaroglu, Djamel Lakehal
Number 3 · December 2005
Table of Contents
Analysis of Severe Accident Management Strategy for a BWR-4 Nuclear Power Plant
Volume 152 · Number 3 · December 2005 · Pages 253-265
Technical Paper · Fission Reactors

Te-Chuan Wang, Shih-Jen Wang, Jyh-Tong Teng
A Feasibility Study of a Steam Methane Reforming Hydrogen Production Plant with a Sodium-Cooled Fast Reactor
Volume 152 · Number 3 · December 2005 · Pages 266-272
Technical Paper · Fission Reactors

Yoshitaka Chikazawa, Mamoru Konomura, Shouji Uchida, Hiroyuki Sato
Ballooning Experiments with VVER Cladding
Volume 152 · Number 3 · December 2005 · Pages 273-285
Technical Paper · Fuel Cycle and Management

Zoltán Hózer, Csaba Gyuori, Márta Horváth, Imre Nagy, László Maróti, Lajos Matus, Péter Windberg, József Frecska
Development and Experimental Verification of the Numerical Simulation Method for the Quasi-Steady SWR Phenomena in an LMR Steam Generator
Volume 152 · Number 3 · December 2005 · Pages 286-301
Technical Paper · Thermal Hydraulics

Jae-Hyuk Eoh, Ji-Young Jeong, Seong-O Kim, Dohee Hahn, Nam-Cook Park
MELCOR Analysis of Steam Generator Tube Creep Rupture in Station Blackout Severe Accident
Volume 152 · Number 3 · December 2005 · Pages 302-313
Technical Paper · Thermal Hydraulics

Y. Liao, K. Vierow
Safety Investigation of Liquid-Metal-Cooled Nuclear Systems with Heat Exchanger in the Risers of Simple Flow-Path Pool Design
Volume 152 · Number 3 · December 2005 · Pages 314-323
Technical Paper · Thermal Hydraulics

Johan Carlsson, Hartmut U. Wider
Computational Analysis of the Thermal-Hydraulic Characteristics of the Encapsulated Nuclear Heat Source
Volume 152 · Number 3 · December 2005 · Pages 324-338
Technical Paper · Thermal Hydraulics

Yoshihisa Nishi, Nobuyuki Ueda, Izumi Kinoshita, Ehud Greenspan
Radioisotope Deposition on Interior Building Surfaces: Air Flow and Surface Roughness Influences
Volume 152 · Number 3 · December 2005 · Pages 339-353
Technical Paper · Decontamination/Decommissioning

Bobby E. Leonard
Monte Carlo-Based Analysis for the Transmutation of Transuranic Waste Recycled in Light Water Reactors
Volume 152 · Number 3 · December 2005 · Pages 354-366
Technical Paper · Radioactive Waste Management and Disposal

Kenneth S. Allen, Edward P. Naessens, Jr.
Neutronics of Minor-Actinide Burning Accelerator-Driven Systems with Ceramic Fuel
Volume 152 · Number 3 · December 2005 · Pages 367-381
Technical Paper · Accelerators

J. Wallenius, M. Eriksson
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