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ANS > Publications > Journals > Nuclear Technology > Volume 158 |
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Number 1 · Number 2 · Number 3 |
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Number 1 · April 2007 |
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• Table of Contents |
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• Introduction (Nusret Aksan, Yassin Hassan) |
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Development of Phenomena Identification and Ranking Tables for the Advanced CANDU Reactor
Volume 158 · Number 1 · April 2007 · Pages 2-17
Technical Paper · Best Estimate Methods  N. K. Popov, H. Sills, A. Abdul-Razzak |
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Evaluation of Weak Heat Conduction Mechanism Model for Long-Term LOCAs in RBMK-1500
Volume 158 · Number 1 · April 2007 · Pages 18-25
Technical Paper · Best Estimate Methods E. Uspuras, A. Kaliatka |
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Accurate Solution of the Nonlinear Partial Differential Equations from Thermal Hydraulics
Volume 158 · Number 1 · April 2007 · Pages 26-35
Technical Paper · Best Estimate Methods Vincent A. Mousseau |
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Detailed MCNP Modeling of BR2 Fuel with Azimuthal Variation
Volume 158 · Number 1 · April 2007 · Pages 36-55
Technical Paper · Best Estimate Methods Silva Kalcheva, Edgar Koonen, Pol Gubel |
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Scaling of the Small-Scale Thermal-Hydraulic Transient to the Real Nuclear Power Plant
Volume 158 · Number 1 · April 2007 · Pages 56-68
Technical Paper · Best Estimate Methods Stojan Petelin, Borut Mavko, Bostjan Koncar, Yassin A. Hassan |
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The State-of-the-Art Theory and Applications of Best-Estimate Plus Uncertainty Methods
Volume 158 · Number 1 · April 2007 · Pages 69-79
Technical Note · Best Estimate Methods Andrej Prosek, Borut Mavko |
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On the Choice Between Segregated and Coupled Solver Approaches When Using Computational Fluid Dynamics for Gas-Cooled Reactor Analysis
Volume 158 · Number 1 · April 2007 · Pages 80-82
Technical Note · Best Estimate Methods David G. Schowalter, Nilanjana Basu, Ajey Walavalkar, Richard R. Schultz |
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Major Challenges to Modeling Aerosol Retention Near a Tube Breach During Steam Generator Tube Rupture Sequences
Volume 158 · Number 1 · April 2007 · Pages 83-93
Technical Paper · Reactor Safety Luis E. Herranz, C. L. del Prá, A. Dehbi |
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Fuel Cycle Analysis of a Subcritical Fast Helium-Cooled Transmutation Reactor with a Fusion Neutron Source
Volume 158 · Number 1 · April 2007 · Pages 94-108
Technical Paper · Radioactive Waste Management and Disposal J. W. Maddox, W. M. Stacey |
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An Investigation of an In-Vessel Corium Retention Strategy for the Wolsong Pressurized Heavy Water Reactor Plants
Volume 158 · Number 1 · April 2007 · Pages 109-115
Technical Note · Thermal Hydraulics Soo-Yong Park, Young-Ho Jin, Yong-Mann Song |
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Number 2 · May 2007 |
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• Table of Contents |
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• Introduction (Hervé Lemonnier, Robert Martin, Joy Rempe) |
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Performance of Planar High-Temperature Electrolysis Stacks for Hydrogen Production from Nuclear Energy
Volume 158 · Number 2 · May 2007 · Pages 118-131
Technical Paper · Nuclear Reactor Thermal Hydraulics James E. O'Brien, Carl M. Stoots, J. Stephen Herring, Joseph J. Hartvigsen |
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Computational Fluid Dynamics Model of a Planar Solid-Oxide Electrolysis Cell for Hydrogen Production from Nuclear Energy
Volume 158 · Number 2 · May 2007 · Pages 132-144
Technical Paper · Nuclear Reactor Thermal Hydraulics Grant L. Hawkes, James E. O'Brien, Carl M. Stoots, J. Stephen Herring, Mehrdad Shahnam |
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Optimization of Advanced High-Temperature Brayton Cycles with Multiple-Reheat Stages
Volume 158 · Number 2 · May 2007 · Pages 145-157
Technical Paper · Nuclear Reactor Thermal Hydraulics Haihua Zhao, Per F. Peterson |
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Hot-Channel Stability of Supercritical Water-Cooled Reactors - I: Steady-State and Sliding Pressure Startup
Volume 158 · Number 2 · May 2007 · Pages 158-173
Technical Paper · Nuclear Reactor Thermal Hydraulics Jiyun Zhao, Pradip Saha, Mujid S. Kazimi |
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Hot-Channel Stability of Supercritical Water-Cooled Reactors - II: Effect of Water Rod Heating and Comparison with BWR Stability
Volume 158 · Number 2 · May 2007 · Pages 174-190
Technical Paper · Nuclear Reactor Thermal Hydraulics Jiyun Zhao, Pradip Saha, Mujid S. Kazimi |
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Development of BWR Regional Stability Experimental Facility SIRIUS-F, Which Simulates Thermal Hydraulics-Neutronics Coupling, and Stability Evaluation of ABWRs
Volume 158 · Number 2 · May 2007 · Pages 191-207
Technical Paper · Nuclear Reactor Thermal Hydraulics Masahiro Furuya, Takanori Fukahori, Shinya Mizokami |
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Investigation of a Passive Condenser System of an Advanced Boiling Water Reactor
Volume 158 · Number 2 · May 2007 · Pages 208-218
Technical Paper · Nuclear Reactor Thermal Hydraulics Seungmin Oh, Haijing Gao, Shripad T. Revankar |
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Critical Heat Flux in Square- and Nonsquare-Array Rod Bundles for Advanced Light Water Reactors
Volume 158 · Number 2 · May 2007 · Pages 219-228
Technical Paper · Nuclear Reactor Thermal Hydraulics Dae-Hyun Hwang, Kyong-Won Seo, Chung-Chan Lee |
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Computational Fluid Dynamics Analysis of Heat Transfer to Heavy Liquid Metals in Bare Rod Bundles
Volume 158 · Number 2 · May 2007 · Pages 229-236
Technical Paper · Nuclear Reactor Thermal Hydraulics X. Cheng, N. I. Tak |
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Improved Turbulence Modeling for Performance Evaluation of Novel Fuel Designs
Volume 158 · Number 2 · May 2007 · Pages 237-248
Technical Paper · Nuclear Reactor Thermal Hydraulics Emilio Baglietto, Hisashi Ninokata |
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Computational Model for Turbulent Flow Around a Grid Spacer with Mixing Vane
Volume 158 · Number 2 · May 2007 · Pages 249-260
Technical Paper · Nuclear Reactor Thermal Hydraulics Tsutomu Ikeno, Takeo Kajishima |
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On the Modeling of Gas Bubble Evolution and Transport Using Coupled Level-Set/CFD Method
Volume 158 · Number 2 · May 2007 · Pages 261-274
Technical Paper · Nuclear Reactor Thermal Hydraulics Bartlomiej Z. Wierzbicki, Steven P. Antal, Michael Z. Podowski |
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Experimental Investigation on Bubble Turbulent Diffusion in a Vertical Large-Diameter Pipe by Wire-Mesh Sensors and Correlation Techniques
Volume 158 · Number 2 · May 2007 · Pages 275-290
Technical Paper · Nuclear Reactor Thermal Hydraulics Annalisa Manera, Horst-Michael Prasser, Dirk Lucas |
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Modeling the Evolution of Bubbly Flow Along a Large Vertical Pipe
Volume 158 · Number 2 · May 2007 · Pages 291-303
Technical Paper · Nuclear Reactor Thermal Hydraulics Dirk Lucas, Eckhard Krepper, H.-M. Prasser |
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Measurement of the Deposition Rate of Droplets in a Vertical Tube Containing a Flow Obstacle
Volume 158 · Number 2 · May 2007 · Pages 304-313
Technical Paper · Nuclear Reactor Thermal Hydraulics Tomio Okawa, Akio Kotani, Naoya Shimada, Isao Kataoka |
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Number 3 · June 2007 |
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• Table of Contents |
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Design and Economic Evaluation of an Advanced Tight-Lattice Core for the IRIS Integral Primary System Reactor
Volume 158 · Number 3 · June 2007 · Pages 315-347
Technical Paper · Fission Reactors J. G. B. Saccheri, N. E. Todreas, M. J. Driscoll |
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Three-Region Core Design for 200-MW(electric) Molten-Salt Reactor with Thorium-Uranium Fuel
Volume 158 · Number 3 · June 2007 · Pages 348-357
Technical Paper · Fission Reactors Koshi Mitachi, Takahisa Yamamoto, Ritsuo Yoshioka |
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Simulation of the Flow Rotation and Mixing in the Downcomer of a VVER-1000 Reactor
Volume 158 · Number 3 · June 2007 · Pages 358-365
Technical Paper · Thermal Hydraulics Emilian Popov, Boyan Ivanov, Kostadin N. Ivanov, Stilyana Mladenova |
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A Study of the Liquid Entrainment and Vapor Pull-Through in an Angled Branch Line
Volume 158 · Number 3 · June 2007 · Pages 366-377
Technical Paper · Thermal Hydraulics Yong Jin Cho, Gyoo Dong Jeun |
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Results of the Triggered Steam Explosions from the TROI Experiment
Volume 158 · Number 3 · June 2007 · Pages 378-395
Technical Paper · Thermal Hydraulics J. H. Kim, I. K. Park, B. T. Min, S. W. Hong, S. H. Hong, J. H. Song, H. D. Kim |
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Assessment of APR1400 ECCS Capability Against Large-Break LOCA Scenario by RELAP5/MOD3 Code
Volume 158 · Number 3 · June 2007 · Pages 396-407
Technical Paper · Thermal Hydraulics Sang Won Lee, Han Gon Kim, Seung Jong Oh |
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Effects of Accelerator-Driven Transmutation System on Radiotoxicity of High-Level Radioactive Wastes
Volume 158 · Number 3 · June 2007 · Pages 408-430
Technical Paper · Radioactive Waste Management and Disposal Joonhong Ahn, Myeongguk Cheon, Ehud Greenspan |
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