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Volume 154

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Number 1

Investigations of Hydraulic Behavior in Spallation Target Configurations

Xu Cheng, Abdalla Batta, Nam-Il Tak

Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 1-12

Technical Paper / Thermal Hydraulics

Internal Vessel Cooling Feasibility Attributed by Critical Heat Flux in Inclined Rectangular Gap

Yong H. Kim, Sung J. Kim, Kune Y. Suh, Joy L. Rempe, F. Bill Cheung, Sang B. Kim

Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 13-40

Technical Paper / Thermal Hydraulics

Neutronic and Safety Aspects of a Gas-Cooled Subcritical Core for Minor Actinide Transmutation

Daniel Westlén, Janne Wallenius

Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 41-51

Technical Paper / Thermal Hydraulics

Subchannel Analysis of Fuel Assemblies of European Experimental ADS

X. Cheng

Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 52-68

Technical Paper / Thermal Hydraulics

Accumulation and Head-Loss Characteristics of Selected Pressurized Water Reactor LOCA-Generated Debris

Ashok K. Ghosh, Arup K. Maji, Mark T. Leonard, Dasari V. Rao, Bruce C. Letellier, Girum S. Urgessa, Scott G. Ashbaugh

Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 69-84

Technical Paper / Thermal Hydraulics

Aerosol Retention Near the Tube Breach During Steam Generator Tube Rupture Sequences

Luis E. Herranz, F. J. S. Velasco, Claudia L. Del Prá

Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 85-94

Technical Paper / Nuclear Plant Operations and Control

Separations and Transmutation Criteria to Improve Utilization of a Geologic Repository

Roald A. Wigeland, Theodore H. Bauer, Thomas H. Fanning, Edgar E. Morris

Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 95-106

Technical Paper / Radioactive Waste Management and Disposal

Results of the QUENCH-09 Experiment Compared to QUENCH-07 with Incorporation of B4C Absorber

L. Sepold, G. Schanz, M. Steinbrück, J. Stuckert, A. Miassoedov, A. Palagin, M. Veshchunov

Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 107-116

Technical Paper / Materials for Nuclear Systems

Measurements of Delayed Fission Product Gamma-Ray Transmission Through Low-Enriched UO2 Fuel Pin Lattices in Air

T. H. Trumbull, D. R. Harris

Nuclear Technology / Volume 154 / Number 1 / April 2006 / Pages 117-127

Technical Paper / Radiation Measurements and Instrumentation

Number 2

Calculation of the Neutron Noise Induced by Shell-Mode Core-Barrel Vibrations in a 1-D, Two-Group, Two-Region Slab Reactor Model

Carl Sunde, Christophe Demazière, Imre Pázsit

Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 129-141

Technical Paper / Fission Reactors

A Conceptual Design Study of a Small Natural Convection Lead-Bismuth-Cooled Reactor Without Refueling for 30 Years

Yoshitaka Chikazawa, Mamoru Konomura, Tomoyasu Mizuno, Makoto Mito, Mikio Tanji

Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 142-154

Technical Paper / Fission Reactors

Formulation of a Single Operational Model for Risk-Informed Applications from the Decoupled Levels 1 and 2 PSA Models

Kwang-Il Ahn, Joon-Eon Yang

Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 155-169

Technical Paper / Reactor Safety

Mass Transfer Modeling With and Without Evaporation for Iodine Chemistry in the Case of a Severe Accident

L. Cantrel, P. March

Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 170-185

Technical Paper / Reactor Safety

MOX Fuel Characterization for Burnup Credit Application: Extension of Nondestructive Method Qualified for LEU Fuels

C. Riffard, H. Toubon, S. Pelletier, M. Batifol, J. M. Vidal

Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 186-193

Technical Paper / Fuel Cycle and Management

Modeling of Radiative Heat Transfer During a PWR Severe Accident

M. Zabiégo, F. Fichot, P. Rubiolo

Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 194-214

Technical Paper / Thermal Hydraulics

The Core Characteristics of a LOCA Power Pulse in a CANDU-6 Reactor with the CANFLEX-RU Fuel

Chang Joon Jeong, Ho Chun Suk

Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 215-223

Technical Paper / Reactor Safety

Continuous Monitoring and Calibration of UTSG Process Sensors by Autoassociative Artificial Neural Network

Marzio Marseguerra, Enrico Zio, Fabio Marcucci

Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 224-236

Technical Paper / Nuclear Plant Operations and Control

Conditions Conducive to Forming Crystalline Uranyl Silicates in High Caustic Nuclear Waste Evaporators

Lawrence N. Oji, Keisha B. Martin, Mary E. Stallings, Martine C. Duff

Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 237-246

Technical Paper / Reprocessing

Thermal-Hydrologic Model Study for an Alternative Waste Package Design for Yucca Mountain Repository

D. Bahrami, G. Danko

Nuclear Technology / Volume 154 / Number 2 / May 2006 / Pages 247-264

Technical Paper / Radioactive Waste Management and Disposal

Number 3

High-Performance Supercritical Carbon Dioxide Cycle for Next-Generation Nuclear Reactors

Vaclav Dostal, Pavel Hejzlar, Michael J. Driscoll

Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 265-282

Technical Paper / Fission Reactors

The Supercritical Carbon Dioxide Power Cycle: Comparison to Other Advanced Power Cycles

Vaclav Dostal, Pavel Hejzlar, Michael J. Driscoll

Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 283-301

Technical Paper / Fission Reactors

Behavior of VVER Fuel Rods Tested Under Severe Accident Conditions in the CODEX Facility

Zoltán Hózer, László Maróti, Péter Windberg, Lajos Matus, Imre Nagy, György Gyenes, Márta Horváth, Anna Pintér, Márton Balaskó, Aladár Czitrovszky, Péter Jani, Attila Nagy, Oleg Prokopiev, Béla Tóth

Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 302-317

Technical Paper / Reactor Safety

Reduction in Workload of BWR In-Core Fuel Shuffling by New Optimization Methods

Akio Yamamoto, Masayuki Toujou, Kentarou Komori, Yasunori Kitamura, Yoshihiro Yamane

Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 318-327

Technical Paper / Fuel Cycle and Management

Analysis of the Bubbly-Churn Regime Transition in a Scaled Model Boiling Water Reactor

Khaled Meftah, Arthur E. Ruggles

Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 328-334

Technical Paper / Thermal Hydraulics

Heat Transfer in a Supercritical Fluid: Classification of Heat Transfer Regimes

Kyoung Woo Seo, Moo Hwan Kim, Mark H. Anderson, Michael L. Corradini

Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 335-349

Technical Paper / Thermal Hydraulics

The Effect of Material Homogenization in Calculating the Gamma-Ray Dose from Spent PWR Fuel Pins in an Air Medium

T. H. Trumbull, D. R. Harris

Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 350-360

Technical Paper / Radiation Protection

Proliferation-Resistant SIGMA Uranium Enrichment Plants

M. E. Rivarola, P. C. Florido, D. O. Brasnarof, K. H. Kyung, L. Juanicó, J. Bergallo, J. Gonzalez, H. Daverio

Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 361-373

Technical Paper / Enrichment

Deterministic Performance Assessment for a Conceptual Repository for Low- and Intermediate-Level Wastes in Korea

Daisuke Kawasaki, Joonhong Ahn, Chang-Lak Kim, Jin-Beak Park

Nuclear Technology / Volume 154 / Number 3 / June 2006 / Pages 374-388

Technical Paper / Radioactive Waste Management and Disposal

 
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