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Volume 153

Number 1 | Number 2 | Number 3

Number 1

Application of the Pitzer Method for Modeling Densities of Actinide Solutions in the SCALE Code System

Charles F. Weber, Calvin M. Hopper

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 1-8

Technical Paper / Reactor Safety

A Methodology for Developing a Probability Distribution for the Failure Enthalpy of High-Burnup Fuels via Simulation

Lorenzo P. Pagani, George E. Apostolakis

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 9-17

Technical Paper / Fuel Cycle and Management

Fission Gas Release from Uranium-Zirconium Hydride Fuel During Heating to Melting

Yeon Soo Kim, Gerard L. Hofman, James L. Snelgrove

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 18-24

Technical Paper / Fuel Cycle and Management

Progress of the DUPIC Fuel Compatibility Analysis - I: Reactor Physics

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

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 25-40

Technical Paper / Fuel Cycle and Management

A Conservative Analysis Methodology for a Steam-Line-Break Accident of the SMART-P Plant

Young-Jong Chung, Hee-Kyung Kim, Hee-Cheol Kim, Sung-Quun Zee

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 41-52

Technical Paper / Thermal Hydraulics

A Generic Method to Evaluate the Reasonable Upper-Bound Dose from Near-Surface Radioactive Waste Disposal Facilities Through Drinking Water Pathway

R. N. Nair, Y. S. Mayya, V. D. Puranik

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 53-69

Technical Paper / Radioactive Waste Management and Disposal

Extracting Risk Insights from Performance Assessments for High-Level Radioactive Waste Repositories

S.Tina Ghosh, George E. Apostolakis

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 70-88

Technical Paper / Radioactive Waste Management and Disposal

The Applicability of a Quenching Mesh as a Hydrogen Flame Arrester in Nuclear Power Plants

Seong-Wan Hong, Jin-Ho Song, Hee-Dong Kim, Soon-Heung Chang

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 89-99

Technical Paper / Miscellaneous

Development of Control Technology for the HTTR Hydrogen Production System

Tetsuo Nishihara, Yoshiyuki Inagaki

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 100-106

Technical Note / Thermal Hydraulics

Alpha-Particle Low-Level Waste Control: Improvement of the PROMETHEE 6 Assay System Performances

Fanny Jallu, Alain Mariani, Christian Passard, Anne-Cecile Raoux, Herve Toubon

Nuclear Technology / Volume 153 / Number 1 / January 2006 / Pages 107-115

Technical Note / Radioactive Waste Management and Disposal

Number 2

On an Improved Design of a Fluidized Bed Nuclear Reactor - I: Design Modifications and Steady-State Features

Alexander Agung, Danny Lathouwers, Tim H. J. J. van der Hagen, Hugo van Dam, Christopher C. Pain, Anthony J. H. Goddard, Matthew D. Eaton, Jefferson L. M. A. Gomes, Bryan Miles, Cassiano R. E. de Oliveira

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 117-131

Technical Paper / Fission Reactors

A Physics Study on Thorium Fuel Recycling in a CANDU Reactor Using Dry Process Technology

Hangbok Choi, Chang Je Park

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 132-145

Technical Paper / Fuel Cycle and Management

Recycle of Transuranium Elements in Light Water Reactors for Reduction of Geological Storage Requirements

E. Fridman, E. Shwageraus, A. Galperin, M. Todosow

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 146-163

Technical Paper / Fuel Cycle and Management

Progress of the DUPIC Fuel Compatibility Analysis - II: Thermal Hydraulics

Joo Hwan Park, Jee-Won Park, Hangbok Choi, Myung Seung Yang

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 164-174

Technical Paper / Thermal Hydraulics

Experiment and RELAP5 Analysis for the Downcomer Boiling of APR1400 Under LBLOCA Reflood Phase

Dong Won Lee, Hee Cheon No, Eu Hwak Lee, Seung Jong Oh, Chul-Hwa Song

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 175-183

Technical Paper / Thermal Hydraulics

Modeling of a Power Conversion System with RELAP5-3D/K and Associated Application to the Feedwater Blowdown Licensing Analysis for the ABWR Containment Design

Thomas K. S. Liang, Chung-Yu Yang, Liang-Che Dai, Fu-Kuang Ko

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 184-196

Technical Paper / Thermal Hydraulics

Computational Fluid Dynamics Predicting the Distributions of Thinning Locations on the Shell Wall of Feedwater Heaters

Y.-M. Ferng, J. H. Hsieh, C. D. Horng

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 197-207

Technical Paper / Thermal Hydraulics

Simulant Melt Experiments on Thermal and Metallurgical Performance of the In-Vessel Core Catcher

Kyoung-Ho Kang, Rae-Joon Park, Sang-Baik Kim, K.Y. Suh, F. B. Cheung, J. L. Rempe

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 208-223

Technical Paper / Thermal Hydraulics

Breeding of 242mAm in a Fast Reactor

Y. Ronen, M. Aboudy, D. Regev

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 224-233

Technical Note / Fuel Cycle and Management

The Temperature Feature on the Step-Up Process of the Hydraulic Control Rod Driving System

Yanhua Zheng, Hanliang Bo, Duo Dong

Nuclear Technology / Volume 153 / Number 2 / February 2006 / Pages 234-239

Technical Note / Thermal Hydraulics

Number 3

The Development of SIMMER-III, An Advanced Computer Program for LMFR Safety Analysis, and Its Application to Sodium Experiments

Y. Tobita, Sa. Kondo, H. Yamano, K. Morita, W. Maschek, P. Coste, T. Cadiou

Nuclear Technology / Volume 153 / Number 3 / March 2006 / Pages 245-255

Technical Paper / Sodium Technology - Thermal Hydraulics

Evaluation of the Accident Scenario Initiated by a Total Instantaneous Blockage in a Phénix Subassembly

Thierry Cadiou, Jacky Louvet

Nuclear Technology / Volume 153 / Number 3 / March 2006 / Pages 256-263

Technical Paper / Sodium Technology - Reactor Safety

Contribution of Phénix to the Development of Transmutation Fuels and Targets in Sodium Fast Breeder Reactors

S. Pillon, F. Sudreau, G. Gaillard-Groléas

Nuclear Technology / Volume 153 / Number 3 / March 2006 / Pages 264-273

Technical Paper / Sodium Technology - Radioactive Waste Management and Disposal

Phénix Steam Generator Module Repair: Sodium Removal Process, Ultrasonic Controls, and Repair Method

Ch. Cavagna, O. Gastaldi, L. Martin, V. Grabon

Nuclear Technology / Volume 153 / Number 3 / March 2006 / Pages 274-281

Technical Note / Sodium Technology - Thermal Hydraulics

Study of Solid Moderators for the Thermal-Spectrum Supercritical Water-Cooled Reactor

Jacopo Buongiorno, James W. Sterbentz, Philip E. MacDonald

Nuclear Technology / Volume 153 / Number 3 / March 2006 / Pages 282-303

Technical Paper / Fission Reactors

Root Cause of Instability in Liquid Zone Control System of CANDU Reactor

Sang-Nyung Kim, Byung-Marn Koh, Joon-Suk Ji

Nuclear Technology / Volume 153 / Number 3 / March 2006 / Pages 304-314

Technical Paper / Thermal Hydraulics

Consequences of Different Types of Contact Between Water and Molten Steel: The ANAIS Experiments

Michel Amblard, Jean-Marc Delhaye, Karine Froment, Jean-Marie Seiler, Bruno Tourniaire

Nuclear Technology / Volume 153 / Number 3 / March 2006 / Pages 315-325

Technical Paper / Thermal Hydraulics

Robust Dynamic Sensor Fault Detection and Isolation of Helical Coil Steam Generator Systems Using a Subspace Identification Technique

Ke Zhao, Belle R. Upadhyaya, Richard T. Wood

Nuclear Technology / Volume 153 / Number 3 / March 2006 / Pages 326-340

Technical Paper / Nuclear Plant Operations and Control

Phenomenology of Baneberry Nuclear Event Revisited with 3-D Finite Element Transient Simulation

Rajeev Ranjan, R. K. Singh, S. K. Sikka, Anil Kakodkar

Nuclear Technology / Volume 153 / Number 3 / March 2006 / Pages 341-359

Technical Paper / Reactor Safety

Evaluation of the Efficiency of Gamma Spectrometers for Analyzing Environmental Samples with Unknown Elemental Composition

Nader M. A. Mohamed, M. Abou Mandour, M. K. Shaat, Alya A. Badawi

Nuclear Technology / Volume 153 / Number 3 / March 2006 / Pages 360-364

Technical Note / Radiation Measurements and Instrumentation

 
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