ANS / Publications / Journals / Nuclear Technology

Hydrogen Production Using High-Temperature Steam Electrolysis Supported by Advanced Gas Reactors with Supercritical CO₂ Cycles

Bilge Yildiz, Katherine J. Hohnholt, Mujid S. Kazimi

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 1-21

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3742

Evaluation of the Impact of SAMG on the Level-2 PSA Results of a Pressurized Water Reactor

Yu-Chih Ko, Ching-Hui Wu, Min Lee

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 22-33

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT06-A3743

Assessment of a Heterogeneous PWR Assembly for Plutonium and Minor Actinide Recycle

T. A. Taiwo, T. K. Kim, J. A. Stillman, R. N. Hill, M. Salvatores, P. J. Finck

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 34-54

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3744

Evaluation of Long-Life Transuranics Breakeven and Burner Cores for Waste Minimization in a PB-GCFR Fuel Cycle

T. A. Taiwo, E. A. Hoffman, R. N. Hill, W. S. Yang

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 55-66

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3745

Feasibility Study on Transient Identification in Nuclear Power Plants Using Support Vector Machines

Christoffer Gottlieb, Vasily Arzhanov, Waclaw Gudowski, Ninos Garis

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 67-77

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT06-A3746

Investigation of Polonium Decontamination from Stainless Steel Surfaces Using the Baking Method

Terumitsu Miura, Toru Obara, Hiroshi Sekimoto

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 78-89

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT06-A3747

Thermal Design of an Alternative Boiling Water Reactor Spent Nuclear Fuel Package for Yucca Mountain Repository

P. Kar, G. Danko, J. S. Armijo, M. Misra, D. Bahrami

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 90-104

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3748

Chemical Thermodynamics Consideration on Corrosion Products in Supercritical-Water-Cooled Reactor Coolant

Norihisa Saito, Yumiko Tsuchiya, Seiji Yamamoto, Yoshie Akai, Tadasu Yotsuyanagi, Masafumi Domae, Yosuke Katsumura

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 105-113

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3749

Chronic Dose Due to a Continuous Tritium Release Calculated by CAP88-PC and NORMTRI

Stacey F. Imboden, Thomas J. Overcamp

Nuclear Technology / Volume 155 / Number 1 / July 2006 / Pages 114-118

Technical Note / Radiation Protection / dx.doi.org/10.13182/NT06-A3750

Prediction of Corrosion Behavior of HLW Containers in the Framework of the French Interim Storage Concept

M. Hélie, Cl. Desgranges, St. Perrin

Nuclear Technology / Volume 155 / Number 2 / August 2006 / Pages 120-132

Technical Paper / Materials / dx.doi.org/10.13182/NT06-A3751

Development and Testing of an Advanced Neutron-Absorbing Gadolinium Alloy for Spent Nuclear Fuel Storage

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

Nuclear Technology / Volume 155 / Number 2 / August 2006 / Pages 133-148

Technical Paper / Materials / dx.doi.org/10.13182/NT06-A3752

The Accelerated Weathering of a Radioactive Low-Activity Waste Glass Under Hydraulically Unsaturated Conditions: Experimental Results from a Pressurized Unsaturated Flow Test

E. M. Pierce, B. P. McGrail, M. M. Valenta, D. M. Strachan

Nuclear Technology / Volume 155 / Number 2 / August 2006 / Pages 149-165

Technical Paper / Materials / dx.doi.org/10.13182/NT06-A3753

Validating a Monte Carlo Model of the University of Wisconsin Nuclear Reactor with Operational Data

Paul W. Humrickhouse, Paul P. H. Wilson

Nuclear Technology / Volume 155 / Number 2 / August 2006 / Pages 166-175

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3754

Progress of the DUPIC Fuel Compatibility Analysis - III: Reactor Safety

Chang Joon Jeong, Bo Wook Rhee, Hangbok Choi, Myung Seung Yang

Nuclear Technology / Volume 155 / Number 2 / August 2006 / Pages 176-191

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3755

Well-to-Wheels Analysis of Energy Use and Greenhouse Gas Emissions of Hydrogen Produced with Nuclear Energy

Ye Wu, Michael Q. Wang, Anant D. Vyas, David C. Wade, Temitope A. Taiwo

Nuclear Technology / Volume 155 / Number 2 / August 2006 / Pages 192-207

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3756

Colloid-Radionuclide Transport Within Fractured Rock: Potential Impact of Nonlinear Sorption Kinetics

Neng-Chuan Tien, Shih-Hai Li

Nuclear Technology / Volume 155 / Number 2 / August 2006 / Pages 208-225

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3757

Mathematical Analysis on Partitioning and Transmutation System with a Two-Member Nuclide Chain

Joonhong Ahn, Paul L. Chambré, Byung-Hyun Park

Nuclear Technology / Volume 155 / Number 2 / August 2006 / Pages 226-247

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT06-A3758

Tritium Measurements in Neutron-Induced Cavitation of Deuterated Acetone

Lefteri Tsoukalas, Franklin Clikeman, Martin Bertodano, Tatjana Jevremovic, Joshua Walter, Anton Bougaev, Edward Merritt

Nuclear Technology / Volume 155 / Number 2 / August 2006 / Pages 248-251

Technical Note / Radiation Measurements and Instrumentation / dx.doi.org/10.13182/NT06-A3759

Development of Drywell Water Level Computational Aid and Application on Containment Flooding Strategy of Mark-III Nuclear Power Plant

Wei-Nian Su, Shih-Jen Wang, I-Ming Huang, Show-Chyuan Chiang

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 253-264

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3760

Full-Height Thermal-Hydraulic Scaling Analysis of Pb-Bi-Cooled Fast Reactor PEACER

Il S. Lee, Kune Y. Suh

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 265-281

Technical Paper / Fission Reactors / dx.doi.org/10.13182/NT06-A3761

Analysis of Pellet-Clad Mechanical Interaction Process of High-Burnup PWR Fuel Rods by RANNS Code in Reactivity-Initiated Accident Conditions

Motoe Suzuki, Toyoshi Fuketa, Hiroaki Saitou

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 282-292

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3762

An Assessment of Fuel Damage in Postulated Reactivity-Initiated Accidents

Ralph O. Meyer

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 293-311

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT06-A3763

A Linear Stability Analysis for Natural-Circulation Loops Under Supercritical Conditions

R. Jain, M. L. Corradini

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 312-323

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3764

Simulant Melt Experiments on In-Vessel Retention Through External Reactor Vessel Cooling

Kyoung-Ho Kang, Rae-Joon Park, Sang-Baik Kim, Hee-Dong Kim, Soon-Heung Chang

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 324-339

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3765

A System Design Study of a Fast Breeder Reactor Hydrogen Production Plant Using Thermochemical and Electrolytic Hybrid Process

Yoshitaka Chikazawa, Toshio Nakagiri, Mamoru Konomura, Shouji Uchida, Yoshihiko Tsuchiyama

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 340-349

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT06-A3766

A ¹⁶N/¹⁹O Monitor for Leak Detection in a Steam Generator

Shengyao Ding, Kun Xu, Xiaojian Huang, Zheng Wang

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 350-357

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT06-A3767

Calculation of Corrosion Rates of Alpha-Doped UO₂

Hilbert Christensen

Nuclear Technology / Volume 155 / Number 3 / September 2006 / Pages 358-364

Technical Paper / Materials for Nuclear Systems / dx.doi.org/10.13182/NT06-A3768