ANS / Publications / Journals / Nuclear Technology

Performance of Planar High-Temperature Electrolysis Stacks for Hydrogen Production from Nuclear Energy

James E. O'Brien, Carl M. Stoots, J. Stephen Herring, Joseph J. Hartvigsen

Nuclear Technology / Volume 158 / Number 2 / May 2007 / Pages 118-131

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3830

Computational Fluid Dynamics Model of a Planar Solid-Oxide Electrolysis Cell for Hydrogen Production from Nuclear Energy

Grant L. Hawkes, James E. O'Brien, Carl M. Stoots, J. Stephen Herring, Mehrdad Shahnam

Nuclear Technology / Volume 158 / Number 2 / May 2007 / Pages 132-144

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3831

Optimization of Advanced High-Temperature Brayton Cycles with Multiple-Reheat Stages

Haihua Zhao, Per F. Peterson

Nuclear Technology / Volume 158 / Number 2 / May 2007 / Pages 145-157

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3832

Hot-Channel Stability of Supercritical Water-Cooled Reactors - I: Steady-State and Sliding Pressure Startup

Jiyun Zhao, Pradip Saha, Mujid S. Kazimi

Nuclear Technology / Volume 158 / Number 2 / May 2007 / Pages 158-173

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3833

Hot-Channel Stability of Supercritical Water-Cooled Reactors - II: Effect of Water Rod Heating and Comparison with BWR Stability

Jiyun Zhao, Pradip Saha, Mujid S. Kazimi

Nuclear Technology / Volume 158 / Number 2 / May 2007 / Pages 174-190

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3834

Development of BWR Regional Stability Experimental Facility SIRIUS-F, Which Simulates Thermal Hydraulics-Neutronics Coupling, and Stability Evaluation of ABWRs

Masahiro Furuya, Takanori Fukahori, Shinya Mizokami

Nuclear Technology / Volume 158 / Number 2 / May 2007 / Pages 191-207

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3835

Investigation of a Passive Condenser System of an Advanced Boiling Water Reactor

Seungmin Oh, Haijing Gao, Shripad T. Revankar

Nuclear Technology / Volume 158 / Number 2 / May 2007 / Pages 208-218

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3836

Critical Heat Flux in Square- and Nonsquare-Array Rod Bundles for Advanced Light Water Reactors

Dae-Hyun Hwang, Kyong-Won Seo, Chung-Chan Lee

Nuclear Technology / Volume 158 / Number 2 / May 2007 / Pages 219-228

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3837

Computational Fluid Dynamics Analysis of Heat Transfer to Heavy Liquid Metals in Bare Rod Bundles

X. Cheng, N. I. Tak

Nuclear Technology / Volume 158 / Number 2 / May 2007 / Pages 229-236

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT158-229

Improved Turbulence Modeling for Performance Evaluation of Novel Fuel Designs

Emilio Baglietto, Hisashi Ninokata

Nuclear Technology / Volume 158 / Number 2 / May 2007 / Pages 237-248

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3839

Computational Model for Turbulent Flow Around a Grid Spacer with Mixing Vane

Tsutomu Ikeno, Takeo Kajishima

Nuclear Technology / Volume 158 / Number 2 / May 2007 / Pages 249-260

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3840

On the Modeling of Gas Bubble Evolution and Transport Using Coupled Level-Set/CFD Method

Bartlomiej Z. Wierzbicki, Steven P. Antal, Michael Z. Podowski

Nuclear Technology / Volume 158 / Number 2 / May 2007 / Pages 261-274

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3841

Experimental Investigation on Bubble Turbulent Diffusion in a Vertical Large-Diameter Pipe by Wire-Mesh Sensors and Correlation Techniques

Annalisa Manera, Horst-Michael Prasser, Dirk Lucas

Nuclear Technology / Volume 158 / Number 2 / May 2007 / Pages 275-290

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3842

Modeling the Evolution of Bubbly Flow Along a Large Vertical Pipe

Dirk Lucas, Eckhard Krepper, H.-M. Prasser

Nuclear Technology / Volume 158 / Number 2 / May 2007 / Pages 291-303

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3843

Measurement of the Deposition Rate of Droplets in a Vertical Tube Containing a Flow Obstacle

Tomio Okawa, Akio Kotani, Naoya Shimada, Isao Kataoka

Nuclear Technology / Volume 158 / Number 2 / May 2007 / Pages 304-313

Technical Paper / Nuclear Reactor Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3844