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Volume 158

Number 1

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

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

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

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

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

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

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

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

Luis E. Herranz, C. L. del PrĂ¡, A. Dehbi

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

Technical Paper / Reactor Safety

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

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

 
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