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Volume 156

Number 3

Assessment of a MOX Fuel Assembly Design for a BWR Mixed Reload

J. Ramon Ramirez, Gustavo Alonso, Robert T. Perry, Javier Ortiz-Villafuerte

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 247-255

Technical Paper / Fuel Cycle and Management

Simulation Capability of the ATLAS Facility for Major Design-Basis Accidents

Ki Yong Choi, Hyun Sik Park, Dong Jin Euh, Tae Soon Kwon, Won Pil Baek

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 256-269

Technical Paper / Thermal Hydraulics

Detailed Analysis of Late-Phase Core-Melt Progression for the Evaluation of In-Vessel Corium Retention

R. J. Park, S. B. Kim, K. Y. Suh, J. L. Rempe, F. B. Cheung

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 270-281

Technical Paper / Thermal Hydraulics

Microgravity Phase Separation for the Rankine Cycle

Melissa Ghrist, Mike Ellis, David Bean, Cable Kurwitz, Frederick Best

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 282-288

Technical Paper / Thermal Hydraulics

A New Approach to Treating the Cell Property Averaging for a System Heat Transfer Analysis

Yoon Sub Sim

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 289-302

Technical Paper / Thermal Hydraulics

Linear Programming Approach for Optimization of Radionuclide Loading in Vitrified HLW

Joonhong Ahn, Myeongguk Cheon

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 303-319

Technical Paper / Radioactive Waste Management and Disposal

Thermocouples for High-Temperature In-Pile Testing

J. L. Rempe, D. L. Knudson, K. G. Condie, S. Curtis Wilkins

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 320-331

Technical Paper / Radiation Measurements and Instrumentation

Review of Literature on Ruthenium Behavior in Nuclear Power Plant Severe Accidents

C. Mun, L. Cantrel, C. Madic

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 332-346

Technical Note / Reactor Safety

Effectiveness of the Raw-Water System as a Severe-Accident-Management Measure in Station Blackout Accidents

Te-Chuan Wang, Shih-Jen Wang, Jyh-Tong Teng

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 347-359

Technical Note / Thermal Hydraulics

Improvement of the Subchannel Flow Mixing Model of the MARS Code

Jae Jun Jeong, Dae Hyun Hwang, Bub Dong Chung

Nuclear Technology / Volume 156 / Number 3 / December 2006 / Pages 360-368

Technical Note / Thermal Hydraulics

 
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