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Volume 169

Number 2

Benchmark Study on Fuel Bundle Degradation in the Phebus FPT2 Test Using State-of-the-Art Severe Accident Analysis Codes

B. Tóth, A. Bieliauskas, G. Bandini, J. Birchley, H. Wada, J. Hohorst, C. Jamond, K. Trambauer

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 81-96

Technical Paper / Reactor Saftey / dx.doi.org/10.13182/NT10-A9354

Modeling Molten Fuel-Moderator Interactions for the CANDU Flow Blockage Accident

Aya Diab, Michael Corradini

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 97-113

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT10-A9355

Long-Term Validation of the Molten Fuel-Moderator Interactions Model

Aya Diab, Michael Corradini, Carl Martin

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 114-125

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT10-A9356

Analysis of Flow Instability for OTSG Using Frequency Domain Control Theory

Suxia Hou, Fuyu Zhao, Yun Tai, Liu Cheng

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 126-133

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT10-A9357

Simulation of the EBR-II Loss-of-Flow Tests Using the MARS Code

Kwi-Seok Ha, Hae-Yong Jeong, Chungho Cho, Young-Min Kwon, Yong-Bum Lee, Dohee Hahn

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 134-142

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT10-A9358

Loading Capacities for Uranium, Plutonium, and Neptunium in High Caustic Nuclear Waste Storage Tanks Containing Selected Sorbents

Lawrence N. Oji, William R. Wilmarth, David T. Hobbs

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 143-149

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT10-A9359

A Container Based on Polymer Composite Materials for the Ultimate Disposal of Spent Nuclear Fuel and Radioactive Waste

H. W. Bonin, J. R. Van Tine, V. T. Bui

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 150-179

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT10-A9360

Estimating Surface Facility Throughput During the Preclosure Emplacement Period at Yucca Mountain

Leah Spradley, Mark Abkowitz, James H. Clarke

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 180-194

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT10-A9361

Analytical and Experimental Investigation of Recent Challenges to Neutron Attenuation and the Relationship with Criticality Analyses

Stanley E. Turner, Thomas G. Haynes III

Nuclear Technology / Volume 169 / Number 2 / February 2010 / Pages 195-203

Technical Note / Radiation Protection / dx.doi.org/10.13182/NT10-A9362

 

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