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ANS > Publications > Journals > Nuclear Technology > Volume 154
Number 1  ·  Number 2  ·  Number 3
Number 1 · April 2006
Table of Contents
Investigations of Hydraulic Behavior in Spallation Target Configurations
Volume 154 · Number 1 · April 2006 · Pages 1-12
Technical Paper · Thermal Hydraulics

Xu Cheng, Abdalla Batta, Nam-Il Tak
Internal Vessel Cooling Feasibility Attributed by Critical Heat Flux in Inclined Rectangular Gap
Volume 154 · Number 1 · April 2006 · Pages 13-40
Technical Paper · Thermal Hydraulics

Yong H. Kim, Sung J. Kim, Kune Y. Suh, Joy L. Rempe, F. Bill Cheung, Sang B. Kim
Neutronic and Safety Aspects of a Gas-Cooled Subcritical Core for Minor Actinide Transmutation
Volume 154 · Number 1 · April 2006 · Pages 41-51
Technical Paper · Thermal Hydraulics

Daniel Westlén, Janne Wallenius
Subchannel Analysis of Fuel Assemblies of European Experimental ADS
Volume 154 · Number 1 · April 2006 · Pages 52-68
Technical Paper · Thermal Hydraulics

X. Cheng
Accumulation and Head-Loss Characteristics of Selected Pressurized Water Reactor LOCA-Generated Debris
Volume 154 · Number 1 · April 2006 · Pages 69-84
Technical Paper · Thermal Hydraulics

Ashok K. Ghosh, Arup K. Maji, Mark T. Leonard, Dasari V. Rao, Bruce C. Letellier, Girum S. Urgessa, Scott G. Ashbaugh
Aerosol Retention Near the Tube Breach During Steam Generator Tube Rupture Sequences
Volume 154 · Number 1 · April 2006 · Pages 85-94
Technical Paper · Nuclear Plant Operations and Control

Luis E. Herranz, F. J. S. Velasco, Claudia L. Del Prá
Separations and Transmutation Criteria to Improve Utilization of a Geologic Repository
Volume 154 · Number 1 · April 2006 · Pages 95-106
Technical Paper · Radioactive Waste Management and Disposal

Roald A. Wigeland, Theodore H. Bauer, Thomas H. Fanning, Edgar E. Morris
Results of the QUENCH-09 Experiment Compared to QUENCH-07 with Incorporation of B4C Absorber
Volume 154 · Number 1 · April 2006 · Pages 107-116
Technical Paper · Materials for Nuclear Systems

L. Sepold, G. Schanz, M. Steinbrück, J. Stuckert, A. Miassoedov, A. Palagin, M. Veshchunov
Measurements of Delayed Fission Product Gamma-Ray Transmission Through Low-Enriched UO2 Fuel Pin Lattices in Air
Volume 154 · Number 1 · April 2006 · Pages 117-127
Technical Paper · Radiation Measurements and Instrumentation

T. H. Trumbull, D. R. Harris
Number 2 · May 2006
Table of Contents
Calculation of the Neutron Noise Induced by Shell-Mode Core-Barrel Vibrations in a 1-D, Two-Group, Two-Region Slab Reactor Model
Volume 154 · Number 2 · May 2006 · Pages 129-141
Technical Paper · Fission Reactors

Carl Sunde, Christophe Demazière, Imre Pázsit
A Conceptual Design Study of a Small Natural Convection Lead-Bismuth-Cooled Reactor Without Refueling for 30 Years
Volume 154 · Number 2 · May 2006 · Pages 142-154
Technical Paper · Fission Reactors

Yoshitaka Chikazawa, Mamoru Konomura, Tomoyasu Mizuno, Makoto Mito, Mikio Tanji
Formulation of a Single Operational Model for Risk-Informed Applications from the Decoupled Levels 1 and 2 PSA Models
Volume 154 · Number 2 · May 2006 · Pages 155-169
Technical Paper · Reactor Safety

Kwang-Il Ahn, Joon-Eon Yang
Mass Transfer Modeling With and Without Evaporation for Iodine Chemistry in the Case of a Severe Accident
Volume 154 · Number 2 · May 2006 · Pages 170-185
Technical Paper · Reactor Safety

L. Cantrel, P. March
MOX Fuel Characterization for Burnup Credit Application: Extension of Nondestructive Method Qualified for LEU Fuels
Volume 154 · Number 2 · May 2006 · Pages 186-193
Technical Paper · Fuel Cycle and Management

C. Riffard, H. Toubon, S. Pelletier, M. Batifol, J. M. Vidal
Modeling of Radiative Heat Transfer During a PWR Severe Accident
Volume 154 · Number 2 · May 2006 · Pages 194-214
Technical Paper · Thermal Hydraulics

M. Zabiégo, F. Fichot, P. Rubiolo
The Core Characteristics of a LOCA Power Pulse in a CANDU-6 Reactor with the CANFLEX-RU Fuel
Volume 154 · Number 2 · May 2006 · Pages 215-223
Technical Paper · Reactor Safety

Chang Joon Jeong, Ho Chun Suk
Continuous Monitoring and Calibration of UTSG Process Sensors by Autoassociative Artificial Neural Network
Volume 154 · Number 2 · May 2006 · Pages 224-236
Technical Paper · Nuclear Plant Operations and Control

Marzio Marseguerra, Enrico Zio, Fabio Marcucci
Conditions Conducive to Forming Crystalline Uranyl Silicates in High Caustic Nuclear Waste Evaporators
Volume 154 · Number 2 · May 2006 · Pages 237-246
Technical Paper · Reprocessing

Lawrence N. Oji, Keisha B. Martin, Mary E. Stallings, Martine C. Duff
Thermal-Hydrologic Model Study for an Alternative Waste Package Design for Yucca Mountain Repository
Volume 154 · Number 2 · May 2006 · Pages 247-264
Technical Paper · Radioactive Waste Management and Disposal

D. Bahrami, G. Danko
Number 3 · June 2006
Table of Contents
High-Performance Supercritical Carbon Dioxide Cycle for Next-Generation Nuclear Reactors
Volume 154 · Number 3 · June 2006 · Pages 265-282
Technical Paper · Fission Reactors

Vaclav Dostal, Pavel Hejzlar, Michael J. Driscoll
The Supercritical Carbon Dioxide Power Cycle: Comparison to Other Advanced Power Cycles
Volume 154 · Number 3 · June 2006 · Pages 283-301
Technical Paper · Fission Reactors

Vaclav Dostal, Pavel Hejzlar, Michael J. Driscoll
Behavior of VVER Fuel Rods Tested Under Severe Accident Conditions in the CODEX Facility
Volume 154 · Number 3 · June 2006 · Pages 302-317
Technical Paper · Reactor Safety

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
Reduction in Workload of BWR In-Core Fuel Shuffling by New Optimization Methods
Volume 154 · Number 3 · June 2006 · Pages 318-327
Technical Paper · Fuel Cycle and Management

Akio Yamamoto, Masayuki Toujou, Kentarou Komori, Yasunori Kitamura, Yoshihiro Yamane
Analysis of the Bubbly-Churn Regime Transition in a Scaled Model Boiling Water Reactor
Volume 154 · Number 3 · June 2006 · Pages 328-334
Technical Paper · Thermal Hydraulics

Khaled Meftah, Arthur E. Ruggles
Heat Transfer in a Supercritical Fluid: Classification of Heat Transfer Regimes
Volume 154 · Number 3 · June 2006 · Pages 335-349
Technical Paper · Thermal Hydraulics

Kyoung Woo Seo, Moo Hwan Kim, Mark H. Anderson, Michael L. Corradini
The Effect of Material Homogenization in Calculating the Gamma-Ray Dose from Spent PWR Fuel Pins in an Air Medium
Volume 154 · Number 3 · June 2006 · Pages 350-360
Technical Paper · Radiation Protection

T. H. Trumbull, D. R. Harris
Proliferation-Resistant SIGMA Uranium Enrichment Plants
Volume 154 · Number 3 · June 2006 · Pages 361-373
Technical Paper · Enrichment

M. E. Rivarola, P. C. Florido, D. O. Brasnarof, K. H. Kyung, L. Juanicó, J. Bergallo, J. Gonzalez, H. Daverio
Deterministic Performance Assessment for a Conceptual Repository for Low- and Intermediate-Level Wastes in Korea
Volume 154 · Number 3 · June 2006 · Pages 374-388
Technical Paper · Radioactive Waste Management and Disposal

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