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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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2024 ANS Annual Conference
June 16–19, 2024
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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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Why should safeguards by design be a global effort?
Jeremy Whitlock
I can’t think of a more exciting time to be working in nuclear, with the diversity of advanced reactor development and increasing global support for nuclear in sustainable energy planning. But we can’t lose sight of the need to plan for efficient international safeguards at the same time.
Global nuclear deployment has been underpinned since 1970 by the Treaty on the Non-Proliferation of Nuclear Weapons (NPT), making it a key customer requirement for governments to demonstrate unequivocally that the technology is not being misused for weapons development.
The International Atomic Energy Agency (IAEA) has helped verify this commitment for more than 50 years, but it has never safeguarded many of the advanced reactors (and related fuel cycle processes) being developed today.
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Safety System Design Concept and Performance Evaluation for a Long Operating Cycle Simplified Boiling Water Reactor
Kenji Arai, Seijiro Suzuki, Mikihide Nakamaru, Hideaki Heki
Nuclear Technology | Volume 143 | Number 1 | July 2003 | Pages 1-10
Technical Paper | Fission Reactors | doi.org/10.13182/NT03-A3393
Rapid-L Operator-Free Fast Reactor Concept Without Any Control Rods
Mitsuru Kambe, Hirokazu Tsunoda, Kaichiro Mishima, Takamichi Iwamura
Nuclear Technology | Volume 143 | Number 1 | July 2003 | Pages 11-21
Technical Paper | Fission Reactors | doi.org/10.13182/NT03-A3394
Performance of Thorium-Based Mixed-Oxide Fuels for the Consumption of Plutonium in Current and Advanced Reactors
Kevan D. Weaver, J. Stephen Herring
Nuclear Technology | Volume 143 | Number 1 | July 2003 | Pages 22-36
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT03-A3395
Coolant Mixing in a Pressurized Water Reactor: Deboration Transients, Steam-Line Breaks, and Emergency Core Cooling Injection
Horst-Michael Prasser, Gerhard Grunwald, Thomas Höhne, Sören Kliem, Ulrich Rohde, Frank-Peter Weiss
Nuclear Technology | Volume 143 | Number 1 | July 2003 | Pages 37-56
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT03-A3396
Multidimensional Mixing Behavior of Steam-Water Flow in a Downcomer Annulus During LBLOCA Reflood Phase with a Direct Vessel Injection Mode
Tae-Soon Kwon, Byong-Jo Yun, Dong-Jin Euh, In-Cheol Chu, Chul-Hwa Song
Nuclear Technology | Volume 143 | Number 1 | July 2003 | Pages 57-64
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT03-A3397
Experimental Study on the Performance of the Passive Safety Injection in an IIST
Chin-Jang Chang, Chien-Hsiung Lee, Wen-Tang Hong, Lance L. C. Wang
Nuclear Technology | Volume 143 | Number 1 | July 2003 | Pages 65-76
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT03-A3398
Stability of Natural-Circulation-Cooled Boiling Water Reactors During Startup: Experimental Results
Annalisa Manera, Tim H. J. J. van der Hagen
Nuclear Technology | Volume 143 | Number 1 | July 2003 | Pages 77-88
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT03-A3399
Critical Power Correlation for Axially Uniformly Heated Tight-Lattice Bundles
Masatoshi Kureta, Hajime Akimoto
Nuclear Technology | Volume 143 | Number 1 | July 2003 | Pages 89-100
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT143-89
Data Reconciliation in the Steam-Turbine Cycle of a Boiling Water Reactor
Svein Sunde, Øivind Berg, Lennart Dahlberg, Nils-Olof Fridqvist
Nuclear Technology | Volume 143 | Number 2 | August 2003 | Pages 103-124
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3401
Out-of-Phase Boiling Water Reactor Stability Monitoring
Miguel Ceceñas-Falcón, Robert M. Edwards
Nuclear Technology | Volume 143 | Number 2 | August 2003 | Pages 125-131
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3402
Hybrid Reactor Simulation of Boiling Water Reactor Power Oscillations
Zhengyu Huang, Robert M. Edwards
Nuclear Technology | Volume 143 | Number 2 | August 2003 | Pages 132-143
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3403
Optimization of a Boiling Water Reactor Loading Pattern Using an Improved Genetic Algorithm
Yoko Kobayashi, Eitaro Aiyoshi
Nuclear Technology | Volume 143 | Number 2 | August 2003 | Pages 144-151
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3404
Impact of Smoke Exposure on Digital Instrumentation and Control
Tina J. Tanaka, Steven P. Nowlen, Kofi Korsah, Richard T. Wood, Christina E. Antonescu
Nuclear Technology | Volume 143 | Number 2 | August 2003 | Pages 152-160
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3405
Updated Aging Assessment Approach and Use with Electric Cable Insulation
David A. Horvath, R. Paul Colaianni
Nuclear Technology | Volume 143 | Number 2 | August 2003 | Pages 161-170
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3406
Microscopic Void Detection for Predicting Remaining Life in Electric Cable Insulation
David A. Horvath, Steven M. Avila
Nuclear Technology | Volume 143 | Number 2 | August 2003 | Pages 171-179
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3407
A Receding Horizon Controller for the Steam Generator Water Level
Man Gyun Na, Yoon Joon Lee
Nuclear Technology | Volume 143 | Number 2 | August 2003 | Pages 180-196
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3408
Experiences Gained from Independent Assessment in Licensing of Advanced I&C Systems in Nuclear Power Plants
Arndt B. Lindner, Dieter H. Wach
Nuclear Technology | Volume 143 | Number 2 | August 2003 | Pages 197-207
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3409
Performance Evaluation of Fabry-Perot Temperature Sensors in Nuclear Power Plant Measurements
Hanying Liu, Don W. Miller, Joseph W. Talnagi
Nuclear Technology | Volume 143 | Number 2 | August 2003 | Pages 208-216
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3410
A Novel Approach to Process Modeling for Instrument Surveillance and Calibration Verification
Brandon Rasmussen, J. Wesley Hines, Robert E. Uhrig
Nuclear Technology | Volume 143 | Number 2 | August 2003 | Pages 217-226
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3411
Initial Experiments on Fuzzy Control for Nuclear Reactor Operations at the Belgian Reactor 1
Da Ruan
Nuclear Technology | Volume 143 | Number 2 | August 2003 | Pages 227-240
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3412
Upgrade of Control and Protection System of the Ignalina Nuclear Power Plant Units 1 and 2
Ronald E. Wright, Norman Fletcher, Raymond D. Pearsall, Victor E. Sidnev, John H. Bickel, Aldo Vianello
Nuclear Technology | Volume 143 | Number 2 | August 2003 | Pages 241-245
Technical Note | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3413
Using Point Reactor Models and Genetic Algorithms for On-Line Global Xenon Estimation in Nuclear Reactors
Tunc Aldemir, Giancarlo Torri, Marzio Marseguerra, Enrico Zio, Jeffrey A. Borkowski
Nuclear Technology | Volume 143 | Number 3 | September 2003 | Pages 247-255
Technical Paper | Fission Reactors | doi.org/10.13182/NT03-A3414
Analysis of Burnup and Economic Potential of Alternative Fuel Materials in Thermal Reactors
Stella Maris Oggianu, Hee Cheon No, Mujid S. Kazimi
Nuclear Technology | Volume 143 | Number 3 | September 2003 | Pages 256-269
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT03-A3415
Maintenance Cycle Extension in the IRIS Advanced Light Water Reactor Plant Design
Mark R. Galvin, Neil E. Todreas, Larry E. Conway
Nuclear Technology | Volume 143 | Number 3 | September 2003 | Pages 270-280
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT03-A3416
Safety Analysis of Fast Reactor Core with Uranium-Free Fuel for Actinide Transmutation
Igor Krivitski, Mikhail Vorotyntsev, Valentin Pyshin, Ludmila Korobeinikova
Nuclear Technology | Volume 143 | Number 3 | September 2003 | Pages 281-289
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT03-A3417
Step Complexity Measure for Emergency Operating Procedures - Determining Weighting Factors
Jinkyun Park, Wondea Jung, Jaewhan Kim, Jaejoo Ha
Nuclear Technology | Volume 143 | Number 3 | September 2003 | Pages 290-308
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT03-A3418
Mobility and Criticality of Plutonium in a Repository
Bernhard Kienzler, Andreas Loida, Werner Maschek, Andrei Rineiski
Nuclear Technology | Volume 143 | Number 3 | September 2003 | Pages 309-321
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT03-A3419
Radionuclide Transport in a Multiple and Parallel Fractured System
Chih-Tien Liu, Hund-Der Yeh
Nuclear Technology | Volume 143 | Number 3 | September 2003 | Pages 322-334
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT03-A3420
The Effective Diffusion Coefficient of Dissolved Oxygen and Oxidation Rate of Pyrite by Dissolved Oxygen in Compacted Purified and Crude Sodium Bentonites in Carbonate Buffered Solution
Mitsuo Manaka
Nuclear Technology | Volume 143 | Number 3 | September 2003 | Pages 335-346
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT03-A3421
Development of Creep Constitutive Equation for Low-Alloy Steel
Kwang J. Jeong, Joon Lim, Il S. Hwang, Hee D. Kim, Martin M. Pilch, Tze Y. Chu
Nuclear Technology | Volume 143 | Number 3 | September 2003 | Pages 347-357
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT03-A3422
Monte Carlo Modeling of the Portuguese Research Reactor Core and Comparison with Experimental Measurements
Ana C. Fernandes, Isabel C. Gonçalves, Nuno P. Barradas, António J. Ramalho
Nuclear Technology | Volume 143 | Number 3 | September 2003 | Pages 358-363
Technical Note | Fission Reactors | doi.org/10.13182/NT03-A3423
Power Profile Evaluation of the JCO Precipitation Vessel Based on the Record of the Gamma-Ray Monitor
Kotaro Tonoike, Takemi Nakamura, Yuichi Yamane, Yoshinori Miyoshi
Nuclear Technology | Volume 143 | Number 3 | September 2003 | Pages 364-372
Technical Note | Reactor Safety | doi.org/10.13182/NT03-A3424