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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
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A Pin Power Reconstruction Method for CANDU Reactor Cores Based on Coarse-Mesh Finite Difference Calculations
Hyung-Seok Lee, Won Sik Yang, Man Gyun Na, Hangbok Choi
Nuclear Technology | Volume 130 | Number 1 | April 2000 | Pages 1-8
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3072
Fission Gas Release from UO2+x in Defective Fuel Rods
Yeon Soo Kim
Nuclear Technology | Volume 130 | Number 1 | April 2000 | Pages 9-17
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3073
RELAP5 Simulation of Thermal-Hydraulic Behavior in a CANDU Reactor - Assessments of RD-14 Experiments
Sukho Lee, In-Goo Kim
Nuclear Technology | Volume 130 | Number 1 | April 2000 | Pages 18-26
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3074
Development of a Dynamic Event Tree for a Pressurized Water Reactor Steam Generator Tube Rupture Event
Chun-Chang Chao, Chin-Jang Chang
Nuclear Technology | Volume 130 | Number 1 | April 2000 | Pages 27-38
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3075
Heat Transfer Modeling During a Vapor Explosion
Georges Berthoud
Nuclear Technology | Volume 130 | Number 1 | April 2000 | Pages 39-58
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3076
Hydrogen Water Chemistry Technology in Boiling Water Reactors
Chien C. Lin
Nuclear Technology | Volume 130 | Number 1 | April 2000 | Pages 59-70
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT00-A3077
Analysis of Radionuclide Release from Spent Ion-Exchange Resins
Sol-Il Su, Man-Sung Yim
Nuclear Technology | Volume 130 | Number 1 | April 2000 | Pages 71-88
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3078
Alternatives to High-Level Waste Vitrification: The Need for Common Sense
Jimmy T. Bell
Nuclear Technology | Volume 130 | Number 1 | April 2000 | Pages 89-98
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3079
A Comparison of Natural Convection Heat Transfer for a Staggered Versus an Aligned Array of Horizontal Spent Nuclear Fuel Rods Within a Rectangular Enclosure
C. Eric Triplett, Robert E. Canaan, Dale E. Klein
Nuclear Technology | Volume 130 | Number 1 | April 2000 | Pages 99-110
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT00-A3080
Criticality and Safety Parameter Studies of a 3-MW TRIGA MARK-II Research Reactor and Validation of the Generated Cross-Section Library and Computational Method
S. I. Bhuiyan, M. A. W. Mondal, M. M. Sarker, M. Rahman, M. S. Shahdatullah, M. Q. Huda, T. K. Chakrobortty, M. J. H. Khan
Nuclear Technology | Volume 130 | Number 2 | May 2000 | Pages 111-131
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3081
A Formal Procedure for Probabilistic Quantification of Modeling Uncertainties Employed in Phenomenological Transient Models
Kwang-Il Ahn, Hee-Dong Kim
Nuclear Technology | Volume 130 | Number 2 | May 2000 | Pages 132-144
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3082
Experimental Breeder Reactor-II Frequency Response Test Measurements Via Pseudorandom, Discrete-Level Binary and Ternary Signals
William D. Rhodes, Raymond V. Furstenau, Howard A. Larson
Nuclear Technology | Volume 130 | Number 2 | May 2000 | Pages 145-158
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3083
Comparisons of Cell Calculations for Uranium-Free Light Water Reactor Fuels
Jean-M. Paratte, Hiroshi Akie, Rakesh Chawla, Marc Delpech, Jan Leen Kloosterman, Carlo Lombardi, Alessandro Mazzola, Sandro Pelloni, Yannick Pénéliau, Hideki Takano
Nuclear Technology | Volume 130 | Number 2 | May 2000 | Pages 159-176
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3084
Comparative Study of Station Blackout Counterpart Tests in APEX and ROSA/AP600
Abd Y. Lafi, Jose N. Reyes, Jr.
Nuclear Technology | Volume 130 | Number 2 | May 2000 | Pages 177-183
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3085
Metal Surface Decontamination Using 1-Hydroxyethane-1,1-Diphosphonic Acid
Michael D. Kaminski, Luis Nuñez, Ankur Purohit, Michael Lewandowski
Nuclear Technology | Volume 130 | Number 2 | May 2000 | Pages 184-195
Technical Paper | Decontamination/Decommissioning | doi.org/10.13182/NT00-A3086
Radioactive Waste Minimization by Electrolytic Extraction and Destruction in a Purex-Truex Actinide Separation System
Masaki Ozawa, Yuichi Sano, Chisako Ohara, Takamichi Kishi
Nuclear Technology | Volume 130 | Number 2 | May 2000 | Pages 196-205
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3087
Measurements of the Effective Diffusion Coefficient of Dissolved Oxygen and Oxidation Rate of Pyrite by Dissolved Oxygen in Compacted Sodium Bentonite
Mitsuo Manaka, Manabu Kawasaki, Akira Honda
Nuclear Technology | Volume 130 | Number 2 | May 2000 | Pages 206-217
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3088
Fracture Mechanism of Borated Stainless Steel
J. Y. He, Salah E. Soliman, Anthony J. Baratta, Thomas A. Balliett
Nuclear Technology | Volume 130 | Number 2 | May 2000 | Pages 218-225
Technical Paper | Materials for Nuclear Systems | doi.org/10.13182/NT00-A3089
Plutonium Recycling in Pressurized Water Reactors: Influence of the Moderator-to-Fuel Ratio
Jan Leen Kloosterman, Evert E. Bende
Nuclear Technology | Volume 130 | Number 3 | June 2000 | Pages 227-241
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3090
A Recriticality-Free Fast Reactor Core Concept
Tetsuo Sawada, Hisashi Ninokata, Hirofumi Tomozoe, Hiroshi Endo
Nuclear Technology | Volume 130 | Number 3 | June 2000 | Pages 242-251
Technical Paper | Fission Reactors | doi.org/10.13182/NT130-242
Fuel Pin Behavior Under the Slow Power Ramp Transients in the CABRI-2 Experiments
Jean Charpenel, Francette Lemoine, Ikken Sato, Dankward Struwe, Werner Pfrang
Nuclear Technology | Volume 130 | Number 3 | June 2000 | Pages 252-271
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3092
Irradiation Experiment on ZrC-Coated Fuel Particles for High-Temperature Gas-Cooled Reactors
Kazuo Minato, Toru Ogawa, Kazuhiro Sawa, Akiyoshi Ishikawa, Takeshi Tomita, Shozo Iida, Hajime Sekino
Nuclear Technology | Volume 130 | Number 3 | June 2000 | Pages 272-281
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3093
In-Core Fuel Management with Biased Multiobjective Function Optimization
Youssef A. Shatilla, David C. Little, Jack A. Penkrot, Richard Andrew Holland
Nuclear Technology | Volume 130 | Number 3 | June 2000 | Pages 282-295
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3094
Analysis of Transient Events Without Scram in a Research Reactor Using the RELAP5/MOD3.2 Computer Code
Sridhar Hari, Yassin A. Hassan, Jiyuan Tu
Nuclear Technology | Volume 130 | Number 3 | June 2000 | Pages 296-309
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3095
A Procedure to Predict Subcooled-Water-Flow-Boiling CHF in Uniformly Heated Tubes for High-Heat-Flux Applications
Young Min Kwon, Soon Heung Chang
Nuclear Technology | Volume 130 | Number 3 | June 2000 | Pages 310-328
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3096
Risk-Informed Assessment of the Technical Specifications of PWR RPS Instrumentation
Ioannis A. Papazoglou
Nuclear Technology | Volume 130 | Number 3 | June 2000 | Pages 329-350
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT00-A3097
An Approximate Reasoning-Based Method for Screening High-Level-Waste Tanks for Flammable Gas
Stephen W. Eisenhawer, Terry F. Bott, Ronald E. Smith
Nuclear Technology | Volume 130 | Number 3 | June 2000 | Pages 351-361
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3098
Interaction Between Molecular Iodine in a Gas Phase and Paints Aged in a Nuclear Power Plant
André Zoulalian, Edith Belval-Haltier
Nuclear Technology | Volume 130 | Number 3 | June 2000 | Pages 362-371
Technical Paper | Radioisotopes | doi.org/10.13182/NT00-A3099
