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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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May 2025
Latest News
INL’s new innovation incubator could link start-ups with an industry sponsor
Idaho National Laboratory is looking for a sponsor to invest $5 million–$10 million in a privately funded innovation incubator to support seed-stage start-ups working in nuclear energy, integrated energy systems, cybersecurity, or advanced materials. For their investment, the sponsor gets access to what INL calls “a turnkey source of cutting-edge American innovation.” Not only are technologies supported by the program “substantially de-risked” by going through technical review and development at a national laboratory, but the arrangement “adds credibility, goodwill, and visibility to the private sector sponsor’s investments,” according to INL.
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Feasibility Assessment of Burnup Credit in the Criticality Analysis of Shipping Casks with Boiling Water Reactor Spent Fuel
Bryan L. Broadhead
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 1-21
Technical Paper | Burnup Credit / Radioactive Waste Management | doi.org/10.13182/NT95-A35092
Evaluation of Burnup Credit for Fuel Storage Analysis—Experience in Spain
Joé M. Conde, Manuel Recio
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 22-32
Technical Paper | Burnup Credit / Nuclear Criticality Safety | doi.org/10.13182/NT95-A35093
Burnup Credit Experiences with the GA-4 Cask
Jack K. Boshoven
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 33-39
Technical Paper | Burnup Credit / Nuclear Criticality Safety | doi.org/10.13182/NT95-A35094
Study on the Criticality Safety Evaluation Method for Burnup Credit in JAERI
Yoshitaka Naito, Makoto Takano, Masayoshi Kurosawa, Takenori Suzaki
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 40-52
Technical Paper | Burnup Credit / Nuclear Crticality Safety | doi.org/10.13182/NT95-A35095
Validation of SCALE-4 for Burnup Credit Applications
Stephen M. Bowman, Mark D. DeHart, Cecil V. Parks
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 53-70
Technical Paper | Burnup Credit / Nuclear Crticality Safety | doi.org/10.13182/NT95-A35096
Three-Dimensional PDQ Validation for Calculating Core Parameters of a Uranium-Aluminide-Fueled Test Reactor
Soon Sam Kim, Jerry L. Judd
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 71-85
Fission Reactor | Burnup Credit | doi.org/10.13182/NT95-A35097
Assessment of a Nuclear Fuel Assembly Performance with Different Inner Water Channels
Gustavo Alonso-Vargas, José L. Montes, Mario R. Perusquía
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 86-92
Fission Reactor | Burnup Credit | doi.org/10.13182/NT95-A35098
A Comparison of Two Versions of a Proposed Test Reactor Using the MCNP Neutronics Code
Salim N. Jahshan, William K. Terry
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 93-105
Fission Reactor | Burnup Credit | doi.org/10.13182/NT95-A35099
Distribution of 16N and 19O in the Reactor Pool Water of the THOR Facility
Chien Chung, Cheng-Chang Chan
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 106-114
Fission Reactor | Burnup Credit | doi.org/10.13182/NT95-A35100
Preliminary Investigation of Actinide and Xenon Reactivity Effects in Accelerator Transmutation of Waste High-Flux Systems
Kenneth R. Olson, Douglass L. Henderson, Michael L. Woosley, Jr., William C. Sailor
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 115-131
Fission Reactor | Burnup Credit | doi.org/10.13182/NT95-A35101
Hybrid Simulation of Boiling Water Reactor Dynamics Using a University Research Reactor
James A. Turso, Robert M. Edwards, Jose March-Leuba
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 132-144
Nuclear Reactor Safety | Burnup Credit | doi.org/10.13182/NT95-A35102
Oxidation/Corrosion of Nb-1 Zr and PWC-11 in Lithium for Space Reactor Applications
James R. DiStefano, James W. Hendricks
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 145-158
Material | Burnup Credit | doi.org/10.13182/NT95-A35103
Sodium-Immersed Self-Cooled Electromagnetic Pump Design and Development of a Large-Scale Coil for High Temperature
Akihiro Oto, Nobuyuki Naohara, Masayoshi Ishida, Toshitaka Kuroki, Kenji Katsuki, Ryouji Kumazawa
Nuclear Technology | Volume 110 | Number 2 | May 1995 | Pages 159-167
Technical Paper | Fission Reactor | doi.org/10.13182/NT95-A35115
Monte Carlo Calculations for Recriticality During the Reflood Phase of a Severe Accident in a Boiling Water Reactor
Russell D. Mosteller, Frank J. Rahn
Nuclear Technology | Volume 110 | Number 2 | May 1995 | Pages 168-180
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35116
Modeling Fission Product Vapor Transport in the Falcon Facility
Iain M. Shepherd, Yannis Drossinos, Christopher G. Benson
Nuclear Technology | Volume 110 | Number 2 | May 1995 | Pages 181-197
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35117
Application of Nonlinear Nodal Diffusion Generalized Perturbation Theory to Nuclear Fuel Reload Optimization
G. Ivan Maldonado, Paul J. Turinsky
Nuclear Technology | Volume 110 | Number 2 | May 1995 | Pages 198-219
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT95-A35118
Design of a Mixer Settler Plant for Isotope Separation by Chemical Exchange
David A. White, Fathurrachman
Nuclear Technology | Volume 110 | Number 2 | May 1995 | Pages 220-227
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT95-A35119
Artificial Neural Networks Optimization Method for Radioactive Source Localization
Eitan Wacholder, Ezra Elias, Yoram Merlis
Nuclear Technology | Volume 110 | Number 2 | May 1995 | Pages 228-237
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT95-A35120
Movement of a Redox Front Around a Repository for High-Level Nuclear Waste
Leonardo Romero, Luis Moreno, Ivars Neretnieks
Nuclear Technology | Volume 110 | Number 2 | May 1995 | Pages 238-249
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT95-A35121
Application of Hydrogen Water Chemistry to Moderate Corrosive Circumstances Around the Reactor Pressure Vessel Bottom of Boiling Water Reactors
Shunsuke Uchida, Eishi Ibe, Kiyatomo Nakata, Motomasa Fuse, Katsumi Ohsumi, Yoshie Takashima
Nuclear Technology | Volume 110 | Number 2 | May 1995 | Pages 250-257
Technical Paper | Material | doi.org/10.13182/NT95-A35122
A Radiometric Water-Level Monitoring System in a High-Pressure Steam Chamber and its Error Analysis
Beicheng Lee, Yuhua Ma, Shengming Jia, Nianzu Lee
Nuclear Technology | Volume 110 | Number 2 | May 1995 | Pages 258-262
Technical Paper | Radioisotope and Isotope | doi.org/10.13182/NT95-A35123
Numerical Analysis of Buoyancy-Driven Exchange Flow with Regard to an HTTR Air Ingress Accident
Motoo Fumizawa, Tomoaki Kunugi, Makoto Hishida, Mikio Akamatsu, Sadao Fujii, Minoru Igarashi
Nuclear Technology | Volume 110 | Number 2 | May 1995 | Pages 263-272
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35124
On Microwave Experiments in Dielectric Media to Simulate Nuclear Volumetric Heating
Cameron R. Bass, Houston G. Wood III
Nuclear Technology | Volume 110 | Number 2 | May 1995 | Pages 273-284
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT95-A35125
Self-Tuning Control of a Nuclear Reactor Using a Gaussian Function Neural Network
Moon Ghu Park, Nam Zin Cho
Nuclear Technology | Volume 110 | Number 2 | May 1995 | Pages 285-293
Technical Paper | Reactor Control | doi.org/10.13182/NT95-A35126
Accelerator Transmutation of Waste Economics
Robert A. Krakowski
Nuclear Technology | Volume 110 | Number 3 | June 1995 | Pages 295-320
Technical Paper | Actinide Burning and Transmutation Special / Nuclear Fuel Cycle | doi.org/10.13182/NT95-A35105
Parametric Systems Studies of the Aqueous-Based (Slurry) Blanket Concept for Accelerator Transmutation of Waste
Carl A. Beard, J. Wiley Davidson, Robert A. Krakowski, Morris E. Battat
Nuclear Technology | Volume 110 | Number 3 | June 1995 | Pages 321-356
Technical Paper | Actinide Burning and Transmutation Special / Nuclear Fuel Cycles | doi.org/10.13182/NT95-A35106
Pyrometallurgical Reprocessing of Fast Reactor Metallic Fuel—Development of A New Electrorefiner with A Ceramic Partition
Tadafumi Koyama, Reiko Fujita, Masatoshi Hzuka, Yukio Sumida
Nuclear Technology | Volume 110 | Number 3 | June 1995 | Pages 357-368
Technical Paper | Actinide Burning and Transmutation Special / Enrichment and Reprocessing System | doi.org/10.13182/NT95-A35107
Preliminary Analysis of the Induced Structural Radioactivity Inventory of the Base-Case Aqueous Accelerator Transmutation of Waste Reactor Concept
Judith A. Bezdecny, Kevin M. Vance, Douglass L. Henderson
Nuclear Technology | Volume 110 | Number 3 | June 1995 | Pages 369-395
Technical Note | Actinide Burning and Transmutation Special / Nuclear Fuel Cycle | doi.org/10.13182/NT95-A35108
Fuel Particle Failure Probabilities and Material Strengths Determined from Crush Test Data
Gregory K. Miller, Derek C. Wadsworth
Nuclear Technology | Volume 110 | Number 3 | June 1995 | Pages 396-406
Technical Paper | Actinide Burning and Transmutation Special / Nuclear Fuel Cycle | doi.org/10.13182/NT95-A35109
In-Pile Measurement of the Thermal Conductivity of Irradiated Metallic Fuel
Theodore H. Bauer, John W. Holland
Nuclear Technology | Volume 110 | Number 3 | June 1995 | Pages 407-421
Technical Paper | Actinide Burning and Transmutation Special / Nuclear Fuel Cycle | doi.org/10.13182/NT95-A35110
Application of High-Frame-Rate Neutron Radiography with A Steady Thermal Neutron Beam to Two-Phase Flow Measurements in A Metallic Rectangular Duct
Takashi Hibiki, Kaichiro Mishima, Masahito Matsubayashi
Nuclear Technology | Volume 110 | Number 3 | June 1995 | Pages 422-435
Technical Paper | Actinide Burning and Transmutation Special / Radiation Application | doi.org/10.13182/NT95-A35111
Nuclear Power Plant Transient Diagnostics Using Artificial Neural Networks That Allow “Don’t-Know” Classifications
Yair bartal, Jie Lin, Robert E. Uhrig
Nuclear Technology | Volume 110 | Number 3 | June 1995 | Pages 436-449
Technical Paper | Actinide Burning and Transmutation Special / Reactor Control | doi.org/10.13182/NT95-A35112
Preliminary Neutronics Investigation of the Delayed Neutron Nondestructive Assay of an Integral Fast Reactor Waste Canister
C.-W. Wu, D. L. Henderson, E. F. Bennett
Nuclear Technology | Volume 110 | Number 3 | June 1995 | Pages 450-454
Department | Actinide Burning and Transmutation Special / Corrigendum | doi.org/10.13182/NT95-A35113
