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Number 1 · July 2006
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Table of Contents
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Hydrogen Production Using High-Temperature Steam Electrolysis Supported by Advanced Gas Reactors with Supercritical CO2 Cycles
Volume 155 · Number 1 · July 2006 · Pages 1-21
Technical Paper · Fission Reactors

Bilge Yildiz, Katherine J. Hohnholt, Mujid S. Kazimi
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Evaluation of the Impact of SAMG on the Level-2 PSA Results of a Pressurized Water Reactor
Volume 155 · Number 1 · July 2006 · Pages 22-33
Technical Paper · Reactor Safety

Yu-Chih Ko, Ching-Hui Wu, Min Lee
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Assessment of a Heterogeneous PWR Assembly for Plutonium and Minor Actinide Recycle
Volume 155 · Number 1 · July 2006 · Pages 34-54
Technical Paper · Fuel Cycle and Management

T. A. Taiwo, T. K. Kim, J. A. Stillman, R. N. Hill, M. Salvatores, P. J. Finck
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Evaluation of Long-Life Transuranics Breakeven and Burner Cores for Waste Minimization in a PB-GCFR Fuel Cycle
Volume 155 · Number 1 · July 2006 · Pages 55-66
Technical Paper · Fuel Cycle and Management

T. A. Taiwo, E. A. Hoffman, R. N. Hill, W. S. Yang
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Feasibility Study on Transient Identification in Nuclear Power Plants Using Support Vector Machines
Volume 155 · Number 1 · July 2006 · Pages 67-77
Technical Paper · Nuclear Plant Operations and Control

Christoffer Gottlieb, Vasily Arzhanov, Waclaw Gudowski, Ninos Garis
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Investigation of Polonium Decontamination from Stainless Steel Surfaces Using the Baking Method
Volume 155 · Number 1 · July 2006 · Pages 78-89
Technical Paper · Nuclear Plant Operations and Control

Terumitsu Miura, Toru Obara, Hiroshi Sekimoto
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Thermal Design of an Alternative Boiling Water Reactor Spent Nuclear Fuel Package for Yucca Mountain Repository
Volume 155 · Number 1 · July 2006 · Pages 90-104
Technical Paper · Radioactive Waste Management and Disposal

P. Kar, G. Danko, J. S. Armijo, M. Misra, D. Bahrami
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Chemical Thermodynamics Consideration on Corrosion Products in Supercritical-Water-Cooled Reactor Coolant
Volume 155 · Number 1 · July 2006 · Pages 105-113
Technical Paper · Radioactive Waste Management and Disposal

Norihisa Saito, Yumiko Tsuchiya, Seiji Yamamoto, Yoshie Akai, Tadasu Yotsuyanagi, Masafumi Domae, Yosuke Katsumura
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Chronic Dose Due to a Continuous Tritium Release Calculated by CAP88-PC and NORMTRI
Volume 155 · Number 1 · July 2006 · Pages 114-118
Technical Note · Radiation Protection

Stacey F. Imboden, Thomas J. Overcamp
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Number 2 · August 2006
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Table of Contents
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Introduction (Ed Kuhn, Dick Blauvelt, Gary Smith)

Book Review (Martin Greenwald)
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Prediction of Corrosion Behavior of HLW Containers in the Framework of the French Interim Storage Concept
Volume 155 · Number 2 · August 2006 · Pages 120-132
Technical Paper · Materials

M. Hélie, Cl. Desgranges, St. Perrin
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Development and Testing of an Advanced Neutron-Absorbing Gadolinium Alloy for Spent Nuclear Fuel Storage
Volume 155 · Number 2 · August 2006 · Pages 133-148
Technical Paper · Materials

Ronald E. Mizia, Tedd E. Lister, Patrick J. Pinhero, Tammy L. Trowbridge, William L. Hurt, Charles V. Robino, John J. Stephens, Jr., John N. DuPont
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The Accelerated Weathering of a Radioactive Low-Activity Waste Glass Under Hydraulically Unsaturated Conditions: Experimental Results from a Pressurized Unsaturated Flow Test
Volume 155 · Number 2 · August 2006 · Pages 149-165
Technical Paper · Materials

E. M. Pierce, B. P. McGrail, M. M. Valenta, D. M. Strachan
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Validating a Monte Carlo Model of the University of Wisconsin Nuclear Reactor with Operational Data
Volume 155 · Number 2 · August 2006 · Pages 166-175
Technical Paper · Fission Reactors

Paul W. Humrickhouse, Paul P. H. Wilson
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Progress of the DUPIC Fuel Compatibility Analysis - III: Reactor Safety
Volume 155 · Number 2 · August 2006 · Pages 176-191
Technical Paper · Fuel Cycle and Management

Chang Joon Jeong, Bo Wook Rhee, Hangbok Choi, Myung Seung Yang
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Well-to-Wheels Analysis of Energy Use and Greenhouse Gas Emissions of Hydrogen Produced with Nuclear Energy
Volume 155 · Number 2 · August 2006 · Pages 192-207
Technical Paper · Fuel Cycle and Management

Ye Wu, Michael Q. Wang, Anant D. Vyas, David C. Wade, Temitope A. Taiwo
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Colloid-Radionuclide Transport Within Fractured Rock: Potential Impact of Nonlinear Sorption Kinetics
Volume 155 · Number 2 · August 2006 · Pages 208-225
Technical Paper · Radioactive Waste Management and Disposal

Neng-Chuan Tien, Shih-Hai Li
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Mathematical Analysis on Partitioning and Transmutation System with a Two-Member Nuclide Chain
Volume 155 · Number 2 · August 2006 · Pages 226-247
Technical Paper · Radioactive Waste Management and Disposal

Joonhong Ahn, Paul L. Chambré, Byung-Hyun Park
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Tritium Measurements in Neutron-Induced Cavitation of Deuterated Acetone
Volume 155 · Number 2 · August 2006 · Pages 248-251
Technical Note · Radiation Measurements and Instrumentation

Lefteri Tsoukalas, Franklin Clikeman, Martin Bertodano, Tatjana Jevremovic, Joshua Walter, Anton Bougaev, Edward Merritt
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Number 3 · September 2006
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Table of Contents
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Corrigendum
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Development of Drywell Water Level Computational Aid and Application on Containment Flooding Strategy of Mark-III Nuclear Power Plant
Volume 155 · Number 3 · September 2006 · Pages 253-264
Technical Paper · Fission Reactors

Wei-Nian Su, Shih-Jen Wang, I-Ming Huang, Show-Chyuan Chiang
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Full-Height Thermal-Hydraulic Scaling Analysis of Pb-Bi-Cooled Fast Reactor PEACER
Volume 155 · Number 3 · September 2006 · Pages 265-281
Technical Paper · Fission Reactors

Il S. Lee, Kune Y. Suh
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Analysis of Pellet-Clad Mechanical Interaction Process of High-Burnup PWR Fuel Rods by RANNS Code in Reactivity-Initiated Accident Conditions
Volume 155 · Number 3 · September 2006 · Pages 282-292
Technical Paper · Fuel Cycle and Management

Motoe Suzuki, Toyoshi Fuketa, Hiroaki Saitou
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An Assessment of Fuel Damage in Postulated Reactivity-Initiated Accidents
Volume 155 · Number 3 · September 2006 · Pages 293-311
Technical Paper · Fuel Cycle and Management

Ralph O. Meyer
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A Linear Stability Analysis for Natural-Circulation Loops Under Supercritical Conditions
Volume 155 · Number 3 · September 2006 · Pages 312-323
Technical Paper · Thermal Hydraulics

R. Jain, M. L. Corradini
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Simulant Melt Experiments on In-Vessel Retention Through External Reactor Vessel Cooling
Volume 155 · Number 3 · September 2006 · Pages 324-339
Technical Paper · Thermal Hydraulics

Kyoung-Ho Kang, Rae-Joon Park, Sang-Baik Kim, Hee-Dong Kim, Soon-Heung Chang
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A System Design Study of a Fast Breeder Reactor Hydrogen Production Plant Using Thermochemical and Electrolytic Hybrid Process
Volume 155 · Number 3 · September 2006 · Pages 340-349
Technical Paper · Thermal Hydraulics

Yoshitaka Chikazawa, Toshio Nakagiri, Mamoru Konomura, Shouji Uchida, Yoshihiko Tsuchiyama
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A 16N/19O Monitor for Leak Detection in a Steam Generator
Volume 155 · Number 3 · September 2006 · Pages 350-357
Technical Paper · Nuclear Plant Operations and Control

Shengyao Ding, Kun Xu, Xiaojian Huang, Zheng Wang
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Calculation of Corrosion Rates of Alpha-Doped UO2
Volume 155 · Number 3 · September 2006 · Pages 358-364
Technical Paper · Materials for Nuclear Systems

Hilbert Christensen
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