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Volume 167

Number 2

Simplification of the Severe Accident Management Guideline for the Containment Flooding in a Mark-III Containment

Min-Jie Chuang, Shih-Jen Wang, Sheng-Yuan Fann, Show-Chyuan Chiang

Nuclear Technology / Volume 167 / Number 2 / August 2009 / Pages 247-253

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT09-A8961

Feasibility Study on an Upgraded Future Monju Core Concept with Extended Operation Cycle Length of One Year and Increased Fuel Burnup

Hidehito Kinjo, Takeshi Kageyama, Akihiro Kitano, Shin Usami

Nuclear Technology / Volume 167 / Number 2 / August 2009 / Pages 254-267

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT09-A8962

Sensitivity and Uncertainty Analysis of Commercial Reactor Criticals for Burnup Credit

Georgeta Radulescu, Donald E. Mueller, John C. Wagner

Nuclear Technology / Volume 167 / Number 2 / August 2009 / Pages 268-287

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT09-A8963

Analysis of a Generic Liquid-Metal Leak

K. Samec, R. Z. Milenkovic

Nuclear Technology / Volume 167 / Number 2 / August 2009 / Pages 288-303

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT09-A8964

Analysis of Leaks Through Microchannel Cracks Using RELAP5-3D

Angelo Frisani, Yassin A. Hassan

Nuclear Technology / Volume 167 / Number 2 / August 2009 / Pages 304-312

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT09-A8965

Use of Geometrically Accurate Fuel Models to Predict Cladding and Basket Temperatures Within a Truck Cask During Normal Transport

Venkata V. R. Venigalla, Miles Greiner

Nuclear Technology / Volume 167 / Number 2 / August 2009 / Pages 313-324

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT09-A8966

Dimensionless Numbers in Phase-Change Thermosyphon and Heat-Pipe Heat Exchangers

Piyush Sabharwall, Vivek Utgikar, Fred Gunnerson

Nuclear Technology / Volume 167 / Number 2 / August 2009 / Pages 325-332

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT09-A8967

Extraction of U(VI) by Tri-n-Amyl Phosphate Under High Solvent Loading Conditions

A. Suresh, N. L. Sreenivasan, Robert Selvan, M. P. Antony, T. G. Srinivasan, S. B. Koganti, P. R. Vasudeva Rao

Nuclear Technology / Volume 167 / Number 2 / August 2009 / Pages 333-338

Technical Note / Reprocessing / dx.doi.org/10.13182/NT09-A8968

 

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