ANS / Publications / Journals / Nuclear Technology

Modernizing and Maintaining Instrumentation and Control Systems in Nuclear Power Plants

Joseph Naser, Raymond Torok, Ramesh Shankar

Nuclear Technology / Volume 141 / Number 1 / January 2003 / Pages 3-9

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3345

Historical Overview, Current Status, and Future Trends in Human-Computer Interfaces for Process Control

Fridtjov Øwre

Nuclear Technology / Volume 141 / Number 1 / January 2003 / Pages 10-32

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3346

Development of an Advanced Digital Reactor Protection System Using Diverse Dual Processors to Prevent Common-Mode Failure

Hyun Kook Shin, Sang Ku Nam, Se Do Sohn, Hoon Seon Chang

Nuclear Technology / Volume 141 / Number 1 / January 2003 / Pages 33-44

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3347

Development of an Automated Approach to Control System Design

José March-Leuba, Richard T. Wood

Nuclear Technology / Volume 141 / Number 1 / January 2003 / Pages 45-53

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3348

On-Line Monitoring and Dynamic Feature Trending as a Means to Improve In-Service Inspection, Maintenance, and Long-Term Assessment of Systems and Components

Dieter H. Wach

Nuclear Technology / Volume 141 / Number 1 / January 2003 / Pages 54-62

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3349

Patterns and Intelligent Systems

Gail A. Cordes

Nuclear Technology / Volume 141 / Number 1 / January 2003 / Pages 63-68

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3350

Integrating Physical Modeling, Neural Computing, and Statistical Analysis for On-Line Process Monitoring

Humberto E. Garcia, Richard B. Vilim

Nuclear Technology / Volume 141 / Number 1 / January 2003 / Pages 69-77

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3351

Development of Simulation-Based Evaluation System for Iterative Design of Human-Machine Interface in a Nuclear Power Plant - Application for Reducing Workload

Motoo Fumizawa, Akiyuki Kameda, Takashi Nakagawa, Wei Wu, Hidekazu Yoshikawa

Nuclear Technology / Volume 141 / Number 1 / January 2003 / Pages 78-87

Technical Paper / Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies / dx.doi.org/10.13182/NT03-A3352

Experimental and Numerical Investigation of Boron Dilution Transients in Pressurized Water Reactors

Roland J. Hertlein, Klaus Umminger, Sören Kliem, Horst-Michael Prasser, Thomas Höhne, Frank-Peter Weiss

Nuclear Technology / Volume 141 / Number 1 / January 2003 / Pages 88-107

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT03-A3353

Assessment of the Load-Carrying Capacities of a Spherical Pressurized Water Reactor Steel Containment Under a Postulated Hydrogen Detonation

R. Krieg, B. Dolensky, B. Göller, W. Breitung, R. Redlinger, P. Royl

Nuclear Technology / Volume 141 / Number 2 / February 2003 / Pages 109-121

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT03-3

Multicycle Optimization of Advanced Gas-Cooled Reactor Loading Patterns Using Genetic Algorithms

A. Kemal Ziver, Jonathan N. Carter, Christopher C. Pain, Cassiano R. E. de Oliveira, Antony J. H. Goddard, Richard S. Overton

Nuclear Technology / Volume 141 / Number 2 / February 2003 / Pages 122-141

Technical Paper / Fuel Cycle and Management / dx.doi.org/10.13182/NT03-A3355

Development of a RELAP5-3D Multidimensional Model of a VVER-1000 NPP for Analysis of a Large-Break Loss-of-Coolant Accident

Kevin T. Clarno, Yassin A. Hassan

Nuclear Technology / Volume 141 / Number 2 / February 2003 / Pages 142-156

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3356

Development and Application of Axially Variable Strength Control Rods for the Power Maneuvering of Pressurized Water Reactors

Ung-Soo Kim, Poong-Hyun Seong

Nuclear Technology / Volume 141 / Number 2 / February 2003 / Pages 157-166

Technical Paper / Nuclear Plant Operations and Control / dx.doi.org/10.13182/NT03-A3357

Vaporization Rate of Cesium from Molten Slag in a Plasma Melting Furnace for the Treatment of Simulated Low-Level Radioactive Wastes

Shinji Yasui, Tadashi Amakawa

Nuclear Technology / Volume 141 / Number 2 / February 2003 / Pages 167-176

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT03-A3358

Using the Monte Carlo Coupling Technique to Evaluate the Shielding Ability of a Modular Shielding House to Accommodate Spent-Fuel Transportable Storage Casks

Kohtaro Ueki, Kazuo Kawakami, Daisuke Shimizu

Nuclear Technology / Volume 141 / Number 2 / February 2003 / Pages 177-185

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT03-A3359

Analysis of Severe Accident Scenarios and Proposals for Safety Improvements for ADS Transmuters with Dedicated Fuel

Werner Maschek, Andrei Rineiski, Michael Flad, Koji Morita, Pierre Coste

Nuclear Technology / Volume 141 / Number 2 / February 2003 / Pages 186-201

Technical Paper / Accelerators / dx.doi.org/10.13182/NT03-A3360

An Approach for Selection of Flow Regime and Models for Conservative Evaluation of a Vessel Integrity Monitoring System for Water-Cooled Vacuum Vessels

W. David Pointer, Arthur E. Ruggles

Nuclear Technology / Volume 141 / Number 2 / February 2003 / Pages 202-210

Technical Note / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3361

The Effect of Pitch, Burnup, and Absorbers on a TRIGA Spent-Fuel Pool Criticality Safety

Marjan Logar, Robert Jeraj, Bogdan Glumac

Nuclear Technology / Volume 141 / Number 2 / February 2003 / Pages 211-219

Technical Note / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT03-A3362

Critical Experiments on 10% Enriched Uranyl Nitrate Solution Using an 80-cm-Diameter Cylindrical Core

Yuichi Yamane, Yoshinori Miyoshi, Shouichi Watanabe, Toshihiro Yamamoto

Nuclear Technology / Volume 141 / Number 3 / March 2003 / Pages 221-232

Technical Paper / Reactor Safety / dx.doi.org/10.13182/NT03-A3363

Theoretical Analysis for Corium Pool with Miscibility Gap

Jean-Marie Seiler, Angélique Fouquet, Karine Froment, Francoise Defoort

Nuclear Technology / Volume 141 / Number 3 / March 2003 / Pages 233-243

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3364

Interaction of Failed Fuel Rods Under Air Ingress Conditions

Zoltán Hózer, Péter Windberg, Imre Nagy, László Maróti, Lajos Matus, Márta Horváth, Anna Pintér Csordás, Márton Balaskó, Aladár Czitrovszky, Péter Jani

Nuclear Technology / Volume 141 / Number 3 / March 2003 / Pages 244-256

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3365

Low-Pressure Corium Dispersion Experiments with Simulant Fluids in a Scaled Annular Cavity

Leonhard Meyer, Mireia G. Gargallo

Nuclear Technology / Volume 141 / Number 3 / March 2003 / Pages 257-274

Technical Paper / Thermal Hydraulics / dx.doi.org/10.13182/NT03-A3366

Wavelet Integrated System to Calculate Radionuclide Release from a Repository in Fractured Media

Hesham R. Nasif, Atsushi Neyama, Hiroyuki Umeki, Atsuyuki Suzuki

Nuclear Technology / Volume 141 / Number 3 / March 2003 / Pages 275-300

Technical Paper / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT03-A3367

Cold-Crucible Induction Melter Design and Development

Dirk Gombert, John R. Richardson

Nuclear Technology / Volume 141 / Number 3 / March 2003 / Pages 301-308

Technical Note / Radioactive Waste Management and Disposal / dx.doi.org/10.13182/NT03-A3368