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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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The uranium market closed out 2024 with a spot price of $72.63 per pound and a long-term price of $80.50 per pound, according to global uranium provider Cameco.
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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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | 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 | doi.org/10.13182/NT03-A3368
