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This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
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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
