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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
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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The deadline is fast approaching for submitting an application to become a technical reviewer for the Nuclear Regulatory Commission’s fiscal year 2025 research grant proposals.
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Stability Monitoring Tests Using a Nuclear-Coupled Boiling Channel Model
Miguel Ceceñas-Falcón, Robert M. Edwards
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 1-11
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3100
Theoretical Derivation of Simplified Evaluation Models for the First Peak of a Criticality Accident in Nuclear Fuel Solution
Yasushi Nomura
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 12-21
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3101
Fission-Product Release During Transient Heating of Irradiated CANDU Fuel
Zhendong Liu, Raymond S. Dickson, Lawrence W. Dickson, Zoran Bilanovic, David S. Cox
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 22-35
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3102
Fission Product Release Behavior of Individual Coated Fuel Particles for High-Temperature Gas-Cooled Reactors
Kazuo Minato, Kazuhiro Sawa, Toshio Koya, Takeshi Tomita, Akiyoshi Ishikawa, Charles A. Baldwin, William Alexander Gabbard, Charlie M. Malone
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 36-47
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3103
FORMOSA-B: A Boiling Water Reactor In-Core Fuel Management Optimization Package II
Atul A. Karve, Paul J. Turinsky
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 48-68
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3104
Application of the Two-Dimensional Navier-Stokes Equations to Steam Cooling in Asymmetrically Heated Channels
L. W. Ward
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 69-81
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3105
Analysis of PANDA Passive Containment Cooling Steady-State Tests with the Spectra Code
Marek M. Stempniewicz
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 82-101
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3106
Current State of Knowledge of Water Radiolysis Effects on Spent Nuclear Fuel Corrosion
H. Christensen, S. Sunder
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 102-123
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3107
Thermal Modeling and Performance Analysis of Interim Dry Storage and Geologic Disposal Facilities for Spent Nuclear Fuel
Si Y. Lee, Robert L. Sindelar, David C. Losey
Nuclear Technology | Volume 131 | Number 1 | July 2000 | Pages 124-151
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3108
The Impact of the Steam-Water Mixture Heterogeneity on the Results of Boiling Water Reactor Cell Calculations
Alexander O. Goltsev, Dmitry N. Martynov, Stanislav V. Marin, Andrei A. Lekomtsev
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 153-158
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3109
Development of a Code with the Capability of Internal Assessment of Uncertainty
Francesco D'Auria, Walter Giannotti
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 159-196
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-5
Parametric Studies on Plutonium Transmutation Using Uranium-Free Fuels in Light Water Reactors
Afroza Shelley, Hiroshi Akie, Hideki Takano, Hiroshi Sekimoto
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 197-209
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3111
Calculated Actinide and Fission Product Concentration Ratios for Gaseous Effluent Monitoring Using Monteburns 3.01
William S. Charlton, Robert T. Perry, Bryan L. Fearey, Theodore A. Parish
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 210-227
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT00-A3112
VVER1000/320 Operational Transient Simulation with the CATHARE Computer Program
Andrey A. Troshko, Yassin A. Hassan
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 228-238
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3113
Localization of a Vibrating Control Rod Pin in Pressurized Water Reactors Using the Neutron Flux and Current Noise
Vasiliy Arzhanov, Imre Pázsit, Ninos S. Garis
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 239-251
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT00-A3114
Rethinking High-Level Waste Disposal: Separate Disposal of High-Heat Radionuclides (90Sr and 137Cs)
Charles W. Forsberg
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 252-268
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3115
Prediction of In-Phantom Dose Distribution Using In-Air Neutron Beam Characteristics for Boron Neutron Capture Synovectomy
Jérôme M. Verbeke, Allen S. Chen, Jasmina L. Vujic, Ka-Ngo Leung
Nuclear Technology | Volume 131 | Number 2 | August 2000 | Pages 269-276
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT00-A3116
Temperature Reactivity Effects in Pebbles of a High-Temperature Reactor Fueled with Reactor-Grade Plutonium
E. E. Bende
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 279-296
Technical Paper | Fission Reactors | doi.org/10.13182/NT00-A3117
LOCA with Consequential or Delayed LOOP: Modeling of Accident Sequences and Associated Core Damage Frequency
Gerardo Martinez-Guridi, Pranab Samanta, Tsong-Lun Chu, Ji-Wu Yang
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 297-318
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3118
Analysis of Kuosheng Large-Break Loss-of-Coolant Accident with MELCOR 1.8.4
Te-Chuan Wang, Shih-Jen Wang, Chun-Sheng Chien
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 319-331
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3119
Formulas Giving Buildup Factor for Double-Layered Shields
Mevlut Guvendik, Nicholas Tsoulfanidis
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 332-336
Technical Paper | Radiation Protection | doi.org/10.13182/NT00-A3120
Effect of Depleted-Uranium Dioxide Particulate Fill on Spent-Nuclear-Fuel Waste Packages
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 337-353
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3121
The Remodeling and Basic Characteristics of the Heavy Water Neutron Irradiation Facility of the Kyoto Univesity Research Reactor, Mainly for Neutron Capture Therapy
Tooru Kobayashi, Yoshinori Sakurai, Keiji Kanda, Yoshiaki Fujita, Koji Ono
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 354-378
Technical Paper | Radiation Biology and Medicine | doi.org/10.13182/NT00-A3122
University Research Reactors: Issues and Challenges
John A. Bernard, Lin-Wen Hu
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 379-384
Technical Note | Fission Reactors | doi.org/10.13182/NT00-A3123
The Physics of Plutonium Fuels - A Review of Organization for Economic Cooperation and Development/Nuclear Energy Agency Activities
Kevin Hesketh, Marc Delpech, Enrico Sartori
Nuclear Technology | Volume 131 | Number 3 | September 2000 | Pages 385-394
Technical Note | Fuel Cycle and Management | doi.org/10.13182/NT00-A3124
