ANS / Publications / Journals / Nuclear Technology

Development of Phenomena Identification and Ranking Tables for the Advanced CANDU Reactor

N. K. Popov, H. Sills, A. Abdul-Razzak

Nuclear Technology / Volume 158 / Number 1 / April 2007 / Pages 2-17

Technical Paper / Best Estimate Methods / dx.doi.org/10.13182/NT07-A3820

Evaluation of Weak Heat Conduction Mechanism Model for Long-Term LOCAs in RBMK-1500

E. Uspuras, A. Kaliatka

Nuclear Technology / Volume 158 / Number 1 / April 2007 / Pages 18-25

Technical Paper / Best Estimate Methods / dx.doi.org/10.13182/NT07-A3821

Accurate Solution of the Nonlinear Partial Differential Equations from Thermal Hydraulics

Vincent A. Mousseau

Nuclear Technology / Volume 158 / Number 1 / April 2007 / Pages 26-35

Technical Paper / Best Estimate Methods / dx.doi.org/10.13182/NT07-A3822

Detailed MCNP Modeling of BR2 Fuel with Azimuthal Variation

Silva Kalcheva, Edgar Koonen, Pol Gubel

Nuclear Technology / Volume 158 / Number 1 / April 2007 / Pages 36-55

Technical Paper / Best Estimate Methods / dx.doi.org/10.13182/NT07-A3823

Scaling of the Small-Scale Thermal-Hydraulic Transient to the Real Nuclear Power Plant

Stojan Petelin, Borut Mavko, Bostjan Koncar, Yassin A. Hassan

Nuclear Technology / Volume 158 / Number 1 / April 2007 / Pages 56-68

Technical Paper / Best Estimate Methods / dx.doi.org/10.13182/NT07-A3824

The State-of-the-Art Theory and Applications of Best-Estimate Plus Uncertainty Methods

Andrej Prosek, Borut Mavko

Nuclear Technology / Volume 158 / Number 1 / April 2007 / Pages 69-79

Technical Note / Best Estimate Methods / dx.doi.org/10.13182/NT07-1

On the Choice Between Segregated and Coupled Solver Approaches When Using Computational Fluid Dynamics for Gas-Cooled Reactor Analysis

David G. Schowalter, Nilanjana Basu, Ajey Walavalkar, Richard R. Schultz

Nuclear Technology / Volume 158 / Number 1 / April 2007 / Pages 80-82

Technical Note / Best Estimate Methods / dx.doi.org/10.13182/NT07-A3826

Major Challenges to Modeling Aerosol Retention Near a Tube Breach During Steam Generator Tube Rupture Sequences

Luis E. Herranz, C. L. del Prá, A. Dehbi

Nuclear Technology / Volume 158 / Number 1 / April 2007 / Pages 83-93

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT07-A3827

Fuel Cycle Analysis of a Subcritical Fast Helium-Cooled Transmutation Reactor with a Fusion Neutron Source

J. W. Maddox, W. M. Stacey

Nuclear Technology / Volume 158 / Number 1 / April 2007 / Pages 94-108

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT07-A3828

An Investigation of an In-Vessel Corium Retention Strategy for the Wolsong Pressurized Heavy Water Reactor Plants

Soo-Yong Park, Young-Ho Jin, Yong-Mann Song

Nuclear Technology / Volume 158 / Number 1 / April 2007 / Pages 109-115

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3829

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

Design and Economic Evaluation of an Advanced Tight-Lattice Core for the IRIS Integral Primary System Reactor

J. G. B. Saccheri, N. E. Todreas, M. J. Driscoll

Nuclear Technology / Volume 158 / Number 3 / June 2007 / Pages 315-347

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT07-A3845

Three-Region Core Design for 200-MW(electric) Molten-Salt Reactor with Thorium-Uranium Fuel

Koshi Mitachi, Takahisa Yamamoto, Ritsuo Yoshioka

Nuclear Technology / Volume 158 / Number 3 / June 2007 / Pages 348-357

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT07-A3846

Simulation of the Flow Rotation and Mixing in the Downcomer of a VVER-1000 Reactor

Emilian Popov, Boyan Ivanov, Kostadin N. Ivanov, Stilyana Mladenova

Nuclear Technology / Volume 158 / Number 3 / June 2007 / Pages 358-365

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3847

A Study of the Liquid Entrainment and Vapor Pull-Through in an Angled Branch Line

Yong Jin Cho, Gyoo Dong Jeun

Nuclear Technology / Volume 158 / Number 3 / June 2007 / Pages 366-377

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3848

Results of the Triggered Steam Explosions from the TROI Experiment

J. H. Kim, I. K. Park, B. T. Min, S. W. Hong, S. H. Hong, J. H. Song, H. D. Kim

Nuclear Technology / Volume 158 / Number 3 / June 2007 / Pages 378-395

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3849

Assessment of APR1400 ECCS Capability Against Large-Break LOCA Scenario by RELAP5/MOD3 Code

Sang Won Lee, Han Gon Kim, Seung Jong Oh

Nuclear Technology / Volume 158 / Number 3 / June 2007 / Pages 396-407

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT07-A3850

Effects of Accelerator-Driven Transmutation System on Radiotoxicity of High-Level Radioactive Wastes

Joonhong Ahn, Myeongguk Cheon, Ehud Greenspan

Nuclear Technology / Volume 158 / Number 3 / June 2007 / Pages 408-430

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT07-A3851