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Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
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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Latest News
Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
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Development of an Expert System for Failure Diagnosis of Primary Side Systems
Se-Woo Cheon, Han-Gon Kim, Wan-Joo Kim, Bok-Ki Min, Soon-Heung Chang, Hak-Yeong Chung
Nuclear Technology | Volume 97 | Number 1 | January 1992 | Pages 1-15
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34621
A Technique for the Selection of the Fuel Pin Diameter for a Uranium/Zirconium Alloy—Fueled Pressurized Water Reactor
Dale B. Lancaster, Robert L. Marsh, Daniel B. Bullen, Holger Pfeifer, C. Steve Erwin, Alan E. Levin+
Nuclear Technology | Volume 97 | Number 1 | January 1992 | Pages 16-26
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34622
A Two-Step Method for Developing a Control Rod Program for Boiling Water Reactors
Mehmet S. Taner, Samuel H. Levine, Ming-Yuan Hsiao
Nuclear Technology | Volume 97 | Number 1 | January 1992 | Pages 27-38
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34623
Framework for Computer-Aided Systems Design
Walter H. Esselman
Nuclear Technology | Volume 97 | Number 1 | January 1992 | Pages 39-51
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34624
On-Line Test of Signal Validation Software on the LOBI-MOD2 Facility in Ispra, Italy
Johannes Prock, Eggert Ohlmer, Michael Labeit
Nuclear Technology | Volume 97 | Number 1 | January 1992 | Pages 52-62
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34625
On-Line Radioiodine Measurement Using Hot Cell Effluent Gases of a Radiopharmaceutical Production Facility
Byung S. Lee, William A. Jester, Joseph M. Olynyk
Nuclear Technology | Volume 97 | Number 1 | January 1992 | Pages 63-70
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34626
Chemical Behavior of Radioiodine in Boiling Water Reactor Systems II: Effects of Hydrogen Water Chemistry
Chien C. Lin
Nuclear Technology | Volume 97 | Number 1 | January 1992 | Pages 71-78
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34627
Nonlinear Identification of Process Dynamics Using Neural Networks
Alexander G. Parlos, Amir F. Atiya, Kil T. Chong, Wei K. Tsai
Nuclear Technology | Volume 97 | Number 1 | January 1992 | Pages 79-96
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34628
Hydrogen Generation Behavior in the LOFT FP-2 and Other Experiments: Comparative Assessment for Mitigated Severe Accident Conditions
August W. Cronenberg
Nuclear Technology | Volume 97 | Number 1 | January 1992 | Pages 97-112
Technical Paper | Reactor Safety | doi.org/10.13182/NT92-A34629
Analysis of Counterpart Tests Performed in Boiling Water Reactor Experimental Simulators
Roberto Bovalini, Francesco D’Auria, Antonio De Varti, Piero Maugeri, Marino Mazzini
Nuclear Technology | Volume 97 | Number 1 | January 1992 | Pages 113-130
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34630
Active Neutron Multiplication Method for Fuel Lattices in Water
Makoto Ueda, Shigeto Kikuchi, Hironori Kumanomido, Takeshi Seino
Nuclear Technology | Volume 97 | Number 1 | January 1992 | Pages 131-141
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT92-A34631
Safety Design Study of Fast Breeder Reactors in Japan
Masanori Miura, Tatsutoshi Inagaki
Nuclear Technology | Volume 97 | Number 2 | February 1992 | Pages 145-152
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34611
Development of Design Guidelines for Seismically Isolated Nuclear Reactors and Research and Development Work Performed by ENEA
Alessandro Martelli, Massimo Forni, Maurizio Indirli, Paolo Masoni, Bruno Spadoni, Giuseppe Bonacina, Giacomo di Pasquale, Tito Sanò, Emil L. Gluekler
Nuclear Technology | Volume 97 | Number 2 | February 1992 | Pages 153-169
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34612
Application of Neural Networks for Sensor Validation and Plant Monitoring
Belle R. Upadhyaya, Evren Eryurek
Nuclear Technology | Volume 97 | Number 2 | February 1992 | Pages 170-176
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34613
Equilibrium and Nonequilibrium Partition Coefficients of Volatile Fission Products Between Liquid Sodium and the Gas Phase
Kazuo Haga, Yukinori Nishizawa, Toshio Watanabe, Shinya Miyahara, Yoshiaki Himeno
Nuclear Technology | Volume 97 | Number 2 | February 1992 | Pages 177-185
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34614
In-Vessel Thermohydraulics Evaluation of an Unprotected Transient Overpower Accident and Delayed Neutron Precursor Concentration Transport Analysis Using a Multidimensional Code
Toshiharu Muramatsu, Hisashi Ninokata
Nuclear Technology | Volume 97 | Number 2 | February 1992 | Pages 186-197
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34615
Performance of Metal and Oxide Fuel Cores During Accidents in Large Liquid-Metal-Cooled Reactors
Peter H. Royl, James E. Cahalan, Günter Friedel, Günter Kussmaul, Jean Moreau, Maurice Perks, Roald A. Wigeland
Nuclear Technology | Volume 97 | Number 2 | February 1992 | Pages 198-211
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34616
Sodium Aerosol Release Rate and Nonvolatile Fission Product Retention Factor During a Sodium-Concrete Reaction
Shinya Miyahara, Kazuo Haga, Yoshiaki Himeno
Nuclear Technology | Volume 97 | Number 2 | February 1992 | Pages 212-226
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34617
Behavior of Breached Mixed-Oxide Fuel Pins During Off-Normal High-Temperature Irradiation
Robert V. Strain, Kenny C. Gross, John D. B. Lambert, Richard P. Colburn, Toshihiro Odo
Nuclear Technology | Volume 97 | Number 2 | February 1992 | Pages 227-240
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34618
A Cost/Risk Framework for Evaluation of Nuclear Waste Management Strategies
William E. Kastenberg, Clyde D. Newman
Nuclear Technology | Volume 97 | Number 2 | February 1992 | Pages 241-251
Technical Paper | Economic | doi.org/10.13182/NT92-A34619
Generation of a Library for Reactor Calculations and Some Applications in Core and Safety Parameter Studies of the 3-MW Triga Mark-II Research Reactor
S. I. Bhuiyan, Anisur Rashid Khan, M. M. Sarker, M. Rahman, Z. Gulshan Ara, M. Musa, M. A. Mannan, I. Mele
Nuclear Technology | Volume 97 | Number 3 | March 1992 | Pages 253-263
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34633
An Axially Multilayered Low Void Worth Liquid-Metal Fast Breeder Reactor Core Concept
Takanobu Kamei, Mitsuaki Yamaoka
Nuclear Technology | Volume 97 | Number 3 | March 1992 | Pages 264-271
Technical Paper | Fission Reactor | doi.org/10.13182/NT92-A34634
Nuclear Power Plant Status Diagnostics Using an Artificial Neural Network
Eric B. Bartlett, Robert E. Uhrig
Nuclear Technology | Volume 97 | Number 3 | March 1992 | Pages 272-281
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34635
Thermal-Hydraulic Analysis of a Hypothetical Complete Failure of One Shroud Access Hole in a Boiling Water Reactor
Lih-Yih Liao
Nuclear Technology | Volume 97 | Number 3 | March 1992 | Pages 282-293
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34636
Depressurization Accidents in a Medium-Sized High-Temperature Gas Reactor: Break Size Parametric Study
Shlomo Ron, Judah Tzoref, Doron Gal
Nuclear Technology | Volume 97 | Number 3 | March 1992 | Pages 294-302
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT92-A34637
Chemotoxicity of Nuclear Waste Repositories
Bernd Buchheim, Lars Persson
Nuclear Technology | Volume 97 | Number 3 | March 1992 | Pages 303-315
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT92-A34638
Zircaloy Cladding Rupture During Repository Storage
Lakshman Santanam, Suresh Raghavan, Bryan A. Chin
Nuclear Technology | Volume 97 | Number 3 | March 1992 | Pages 316-322
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT92-A34639
Modeling for Migration of a Redox-Sensitive Radionuclide in Engineered Barriers
Joonhong Ahn, Shinichi Nakayama
Nuclear Technology | Volume 97 | Number 3 | March 1992 | Pages 323-335
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT92-A34640
Dynamic Strain-Aging Effect on Fracture Toughness of Vessel Steels
Sung Sik Kang, In Sup Kim
Nuclear Technology | Volume 97 | Number 3 | March 1992 | Pages 336-343
Technical Paper | Material | doi.org/10.13182/NT92-A34641
Three-Dimensional Thermal Aspects of Aluminum Fuel Elements
Robert P. Wadkins, Richard G. Ambrosek
Nuclear Technology | Volume 97 | Number 3 | March 1992 | Pages 344-351
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34642
Development of an Efficient Three-Dimensional Reactor Core Model for Simulator Applications
Mankit Ray Yeung, Guo Bing Jiang
Nuclear Technology | Volume 97 | Number 3 | March 1992 | Pages 352-361
Technical Paper | Reactor Operation | doi.org/10.13182/NT92-A34643
Life Testing of a Low-Voltage Air Circuit Breaker to Assess Age-Related Degradation
Mano Subudhi
Nuclear Technology | Volume 97 | Number 3 | March 1992 | Pages 362-370
Technical Paper | Reactor Operation | doi.org/10.13182/NT92-A34644
