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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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Energy Forecasting in the Preparation of French Plan VII
Marc Alinhac
Nuclear Technology | Volume 39 | Number 1 | June 1978 | Pages 5-9
Technical Paper | Energy Modeling and Forecasting / Reactor | doi.org/10.13182/NT78-A17001
Energy Modeling and Forecasting at the U.S. Energy Research and Development Administration
Richard H. Williamson, Edward J. Hanrahan
Nuclear Technology | Volume 39 | Number 1 | June 1978 | Pages 10-17
Technical Paper | Energy Modeling and Forecasting / Reactor | doi.org/10.13182/NT78-A17002
Risk Analysis of Radioactive Waste Management Systems in Germany
Hans J. Wingender
Nuclear Technology | Volume 39 | Number 1 | June 1978 | Pages 18-24
Nuclear Safety Analysis | Energy Modeling and Forecasting / Radioactive Waste | doi.org/10.13182/NT78-A17003
Contributions to the Risk Evaluation of a High-Level Waste Solidification Plant
H. Brücher
Nuclear Technology | Volume 39 | Number 1 | June 1978 | Pages 25-29
Nuclear Safety Analysis | Energy Modeling and Forecasting / Radioactive Waste | doi.org/10.13182/NT78-A17004
Transient Analyses of a 1000-MW Gas-Cooled Fast Reactor
Dirk Wilhelm
Nuclear Technology | Volume 39 | Number 1 | June 1978 | Pages 30-40
Nuclear Safety Analysis | Energy Modeling and Forecasting / Reactor | doi.org/10.13182/NT78-A17005
Containment Negative Pressure Evaluation
Stephen W. Webb
Nuclear Technology | Volume 39 | Number 1 | June 1978 | Pages 41-45
Nuclear Safety Analysis | Energy Modeling and Forecasting / Reactor | doi.org/10.13182/NT78-A17006
Optimum Fuel Loading and Operation Planning for Light Water Reactor Power Stations. Part I: Pressurized Water Reactor Case Study
Tsutomu Hoshino
Nuclear Technology | Volume 39 | Number 1 | June 1978 | Pages 46-62
Nuclear Safety Analysis | Energy Modeling and Forecasting / Fuel Cycle | doi.org/10.13182/NT78-A17007
Electrochemical Extraction of Hydrogen from Molten LiF-LiCI-LiBr and Its Application to Liquid-Lithium Fusion Reactor Blanket Processing
W. F. Calaway
Nuclear Technology | Volume 39 | Number 1 | June 1978 | Pages 63-74
Nuclear Safety Analysis | Energy Modeling and Forecasting / Chemical Processing | doi.org/10.13182/NT78-A17008
Corrosion and Mechanical Behavior of Iron in Liquid Lithium
T. A. Whipple, D. L. Olson, W. L. Bradley, D. K. Matlock
Nuclear Technology | Volume 39 | Number 1 | June 1978 | Pages 75-83
Nuclear Safety Analysis | Energy Modeling and Forecasting / Material | doi.org/10.13182/NT78-A17009
Europia as a Nuclear Control Material
Paul C. S. Wu
Nuclear Technology | Volume 39 | Number 1 | June 1978 | Pages 84-94
Nuclear Safety Analysis | Energy Modeling and Forecasting / Material | doi.org/10.13182/NT78-A17010
Analysis of Fissile Materials by Cyclic Activation of Delayed Neutrons
John M. Jamieson, Geoffrey G. Eichholz
Nuclear Technology | Volume 39 | Number 1 | June 1978 | Pages 95-100
Nuclear Safety Analysis | Energy Modeling and Forecasting / Analysis | doi.org/10.13182/NT78-A17011
Some In-Reactor Loop Experiments on Corrosion Product Transport and Water Chemistry
P. V. Balakrishnan, G. M. Allison
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 105-120
Technical Paper | Reactor | doi.org/10.13182/NT78-A32072
A Mechanistic Study of Fuel Freezing, Channel Plugging, and Continued Coolability During Fast Reactor Overpower Excursions
Kin Wah Wong, Vijay K. Dhir, W. E. Kastenberg
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 121-137
Technical Paper | Reactor | doi.org/10.13182/NT78-A32073
Development Work for a Borax Internal Core-Catcher for a Gas-Cooled Fast Reactor
M. Dalle Donne, S. Dorner, G. Schumacher
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 138-154
Technical Paper | Reactor | doi.org/10.13182/NT78-A32074
Hydraulic Force Calculation with Hydro-Structural Interactions
K. Takeuchi
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 155-166
Technical Paper | Reactor | doi.org/10.13182/NT78-A32075
Liquid-Metal Fast Breeder Reactor Fuel Rod Performance and Modeling at High Burnup
P. Verbeek, H. Tbbe, N. Hoppe, B. Steinmetz
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 167-185
Technical Paper | Fuel | doi.org/10.13182/NT78-A32076
Model for Life-Limiting Properties of Fusion Reactor Structural Materials
R. F. Mattas, D. L. Smith
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 186-198
Technical Paper | Material | doi.org/10.13182/NT78-A32077
Effect of Prior Irradiation Creep on the Subsequent Burst Strength of 20% Cold-Worked Type 316 Stainless-Steel Cladding
D. R. Duncan
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 199-206
Technical Paper | Material | doi.org/10.13182/NT78-A32078
Irradiation Temperature Determination by Electrical Resistivity Measurements
F. Lee, J. Matolich, Jr., J. Moteff
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 207-212
Technical Paper | Material | doi.org/10.13182/NT78-A32079
Hydrogen Burden from the Steam Side Corrosion in Sodium-Heated Steam Generators
Prodyot Roy, Douglas N. Rodgers
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 213-215
Technical Note | Analysis | doi.org/10.13182/NT78-A32080
Electrochemical Oxygen Sensor for Measurement of Oxygen in Liquid Sodium
Prodyot Roy, Bruce E. Bugbee
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 216-218
Technical Note | Analysis | doi.org/10.13182/NT78-A32081
Primary Pipe Rupture Accident Analysis for the Clinch River Breeder Reactor
Dennis C. Albright, Robert A. Bari
Nuclear Technology | Volume 39 | Number 3 | August 1978 | Pages 225-257
Technical Paper | Reactor | doi.org/10.13182/NT78-A32054
Limitations on Tritium Transport Through Fusion Reactors
Andrew S. Zarchy, Robert C. Axtmann
Nuclear Technology | Volume 39 | Number 3 | August 1978 | Pages 258-265
Technical Paper | Reactor | doi.org/10.13182/NT78-A32055
The Use of Nuclear Systematics to Estimate Gamma Spectra
Gene D. Holter, Stephen E. Binney
Nuclear Technology | Volume 39 | Number 3 | August 1978 | Pages 266-274
Technical Paper | Reactor | doi.org/10.13182/NT78-A32056
Recent Improvements in Identifying Fission Product Sources in the Experimental Breeder Reactor II
J. D. B. Lambert, B. Y. C. So, F. S. Kirn, J. R. Armstrong, E. R. Ebersole, M. T. Laug
Nuclear Technology | Volume 39 | Number 3 | August 1978 | Pages 275-282
Technical Paper | Reactor | doi.org/10.13182/NT78-4
LOWI, A New Zircaloy-UO2 Fuel Design: Design Considerations, Calculations, and Test Results
Arne Jensen
Nuclear Technology | Volume 39 | Number 3 | August 1978 | Pages 283-288
Technical Paper | Fuel | doi.org/10.13182/NT78-A32058
Investigation of Irradiated Uranium-Plutonium Carbonitride Fuel by Microprobe Analysis
C. T. Walker
Nuclear Technology | Volume 39 | Number 3 | August 1978 | Pages 289-296
Technical Paper | Material | doi.org/10.13182/NT78-A32059
On the Characterization of Elasto-Plastic Material Behavior Using the Concepts of Crack Opening Stretch and J Integral
Thomas Hollstein, Johann Georg Blauel
Nuclear Technology | Volume 39 | Number 3 | August 1978 | Pages 297-310
Technical Paper | Material | doi.org/10.13182/NT78-A32060
On Compressible Flow in a Gas Centrifuge and Its Effect on the Maximum Separative Power
J. J. H. Brouwers
Nuclear Technology | Volume 39 | Number 3 | August 1978 | Pages 311-322
Technical Paper | Isotopes Separation | doi.org/10.13182/NT78-A32061
A Simple Relationship of Maximum Δk due to Compaction of Unmoderated Fissile Materials
Charles R. Marotta
Nuclear Technology | Volume 39 | Number 3 | August 1978 | Pages 323-326
Technical Note | Chemical Processing | doi.org/10.13182/NT78-A32062
