ANS / Publications / Journals / Nuclear Technology

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 / dx.doi.org/10.13182/NT05-A3657

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 / dx.doi.org/10.13182/NT152-23

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 / dx.doi.org/10.13182/NT05-3

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 / dx.doi.org/10.13182/NT05-A3660

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 / dx.doi.org/10.13182/NT05-A3661

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 / dx.doi.org/10.13182/NT152-87

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 / dx.doi.org/10.13182/NT05-A3663

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 / dx.doi.org/10.13182/NT05-A3664

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 / dx.doi.org/10.13182/NT05-A3665

Limiting Factors for External Reactor Vessel Cooling

F. B. Cheung

Nuclear Technology / Volume 152 / Number 2 / November 2005 / Pages 145-161

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3666

Critical Heat Flux Experiments on the Reactor Vessel Wall Using 2-D Slice Test Section

Yong Hoon Jeong, Soon Heung Chang, Won-Pil Baek

Nuclear Technology / Volume 152 / Number 2 / November 2005 / Pages 162-169

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3667

Development of an Enhanced Core Catcher for Improving In-Vessel Retention Margins

J. L. Rempe, K. G. Condie, D. L. Knudson, K. Y. Suh, F. B. Cheung, S. B. Kim

Nuclear Technology / Volume 152 / Number 2 / November 2005 / Pages 170-182

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3668

KAERI Integral Effect Test Program and the ATLAS Design

Won-Pil Baek, Chul-Hwa Song, Byong-Jo Yun, Tae-Soon Kwon, Sang-Ki Moon, Sung-Jae Lee

Nuclear Technology / Volume 152 / Number 2 / November 2005 / Pages 183-195

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3669

Evolution of Design Methodologies for Next Generation of Reactor Pressure Vessels and Extensive Role of Thermal-Hydraulic Numerical Tools

Serge Bellet, Nicolas Goreaud, Norbert Nicaise

Nuclear Technology / Volume 152 / Number 2 / November 2005 / Pages 196-209

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3670

Experimental Study on Flow Optimization in Upper Plenum of Reactor Vessel for a Compact Sodium-Cooled Fast Reactor

Nobuyuki Kimura, Kenji Hayashi, Hideki Kamide, Masami Itoh, Tadashi Sekine

Nuclear Technology / Volume 152 / Number 2 / November 2005 / Pages 210-222

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3671

Computational Study of Thermal Striping in an Upper Plenum of Kalimer

Seok-Ki Choi, Myung-Hwan Wi, Won-Dae Jeon, Seong-O Kim

Nuclear Technology / Volume 152 / Number 2 / November 2005 / Pages 223-238

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3672

New Challenges in Computational Thermal Hydraulics

George Yadigaroglu, Djamel Lakehal

Nuclear Technology / Volume 152 / Number 2 / November 2005 / Pages 239-251

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3673

Analysis of Severe Accident Management Strategy for a BWR-4 Nuclear Power Plant

Te-Chuan Wang, Shih-Jen Wang, Jyh-Tong Teng

Nuclear Technology / Volume 152 / Number 3 / December 2005 / Pages 253-265

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT05-A3674

A Feasibility Study of a Steam Methane Reforming Hydrogen Production Plant with a Sodium-Cooled Fast Reactor

Yoshitaka Chikazawa, Mamoru Konomura, Shouji Uchida, Hiroyuki Sato

Nuclear Technology / Volume 152 / Number 3 / December 2005 / Pages 266-272

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT05-A3675

Ballooning Experiments with VVER Cladding

Zoltán Hózer, Csaba Gyuori, Márta Horváth, Imre Nagy, László Maróti, Lajos Matus, Péter Windberg, József Frecska

Nuclear Technology / Volume 152 / Number 3 / December 2005 / Pages 273-285

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT05-A3676

Development and Experimental Verification of the Numerical Simulation Method for the Quasi-Steady SWR Phenomena in an LMR Steam Generator

Jae-Hyuk Eoh, Ji-Young Jeong, Seong-O Kim, Dohee Hahn, Nam-Cook Park

Nuclear Technology / Volume 152 / Number 3 / December 2005 / Pages 286-301

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3677

MELCOR Analysis of Steam Generator Tube Creep Rupture in Station Blackout Severe Accident

Y. Liao, K. Vierow

Nuclear Technology / Volume 152 / Number 3 / December 2005 / Pages 302-313

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-5

Safety Investigation of Liquid-Metal-Cooled Nuclear Systems with Heat Exchanger in the Risers of Simple Flow-Path Pool Design

Johan Carlsson, Hartmut U. Wider

Nuclear Technology / Volume 152 / Number 3 / December 2005 / Pages 314-323

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3679

Computational Analysis of the Thermal-Hydraulic Characteristics of the Encapsulated Nuclear Heat Source

Yoshihisa Nishi, Nobuyuki Ueda, Izumi Kinoshita, Ehud Greenspan

Nuclear Technology / Volume 152 / Number 3 / December 2005 / Pages 324-338

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT05-A3680

Radioisotope Deposition on Interior Building Surfaces: Air Flow and Surface Roughness Influences

Bobby E. Leonard

Nuclear Technology / Volume 152 / Number 3 / December 2005 / Pages 339-353

Technical Paper / Decontamination/Decommissioning / dx.doi.org/10.13182/NT05-A3681

Monte Carlo-Based Analysis for the Transmutation of Transuranic Waste Recycled in Light Water Reactors

Kenneth S. Allen, Edward P. Naessens, Jr.

Nuclear Technology / Volume 152 / Number 3 / December 2005 / Pages 354-366

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT05-A3682

Neutronics of Minor-Actinide Burning Accelerator-Driven Systems with Ceramic Fuel

J. Wallenius, M. Eriksson

Nuclear Technology / Volume 152 / Number 3 / December 2005 / Pages 367-381

Technical Paper / Accelerators / dx.doi.org/10.13182/NT152-367