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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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Nuclear Technology
Fusion Science and Technology
Latest News
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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Use of Zero Power Plutonium Reactor Measurements as a Support of Criticality Prediction for the SNR-300
S. Pilate, R. de Wouters, U. Wehmann, F. Helm, W. Scholtyssek
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 5-11
Technical Paper | Reactor | doi.org/10.13182/NT78-A32128
Tritium Pathways and Handling Problems in a Laser Fusion Reactor
Edwin M. Larsen, S. I. Abdel-Khalik, Mark S. Ortman
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 12-26
Technical Paper | Reactor | doi.org/10.13182/NT78-A32129
Improved Load Follow Strategy for Return-to-Power Capability
C. E. Meyer, C. L. Bennett, D. J. Hill, K. J. Dzikowski
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 27-35
Technical Paper | Reactor | doi.org/10.13182/NT78-A32130
A Generalized Treatment of Heterogeneity Effects for the Shielding Factor Method
E. Kujawski, R. Protsik
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 36-45
Technical Paper | Reactor | doi.org/10.13182/NT78-A32131
Denatured Fuel Cycles for International Safeguards
T. H. Pigford, C. S. Yang, M. Maeda
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 46-59
Technical Paper | Fuel Cycle | doi.org/10.13182/NT78-A32132
Actinide Redistribution in the Outer Regions of Mixed-Oxide Fuel
L. A. Lawrence, D. C. Hata, D. F. Washburn
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 60-70
Technical Paper | Fuel | doi.org/10.13182/NT78-A32133
Radiation Shielding of Major Penetrations in Tokamak Reactors
Jungchung Jung, Mohamed A. Abdou
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 71-86
Technical Paper | Shielding | doi.org/10.13182/NT78-A32134
Calculation of Spatial Weighting Functions for Ex-Core Neutron Detectors
Mark W. Crump, John C. Lee
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 87-96
Technical Paper | Instrument | doi.org/10.13182/NT78-A32135
Reliability, Reliability with Repair, and Availability of Four Identical Element Multiplex Systems
Richard D. Guild, Edmond G. Tourigny
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 97-108
Technical Paper | Technique | doi.org/10.13182/NT78-A32136
Development and Testing of Neutron Dosimetry Techniques for Accelerator-Based Irradiation Facilities
L. R. Greenwood, R. R. Heinrich, R. J. Kennerley, R. Medrzychowski+
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 109-128
Technical Paper | Technique | doi.org/10.13182/NT78-A32137
The Effect of Drop Evaporation Rate on Containment Pressure Transients
Kazys K. Almenas, Joseph M. Marchello
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 263-275
Technical Paper | Reactor | doi.org/10.13182/NT78-A32112
An Assessment of the Consequences of Boiling in the Radial Blanket due to Hypothetical Major Pipe Leaks
N. Prasad Kadambi, Roger W. Tilbrook
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 276-282
Technical Paper | Reactor | doi.org/10.13182/NT78-A32113
A Space-Time Analysis of Void Reactivity Feedback in Boiling Water Reactors
Hsiang-Shou Cheng, Ming-Shih Lu, David J. Diamond
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 283-298
Technical Paper | Reactor | doi.org/10.13182/NT78-A32114
Sputtering Erosion in Inertial Confinement Fusion Reactors
I. O. Bohachevsky, J. F. Hafer
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 299-311
Technical Paper | Reactor | doi.org/10.13182/NT78-A32115
An SAS3D Analysis of Unprotected Loss-of-Flow Transients for 1200-MW(electric) Liquid-Metal Fast Breeder Reactor Homogeneous and Heterogeneous Core Designs
T. A. Shih, M. I. Temme
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 312-322
Technical Paper | Reactor | doi.org/10.13182/NT78-A32116
Extraction of Actinide Elements by Trilaurylammonium Nitrate Carboxylic Acid Mixtures and Applications
Charles Madic, Gerard Koehly
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 323-340
Technical Paper | Chemical Processing | doi.org/10.13182/NT78-A32117
Safety Calculations and Benchmarking of Babcock and Wilcox Designed Close Spaced Fuel Storage Racks
William D. Bromley, James S. Olszewski
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 341-348
Technical Paper | Chemical Processing | doi.org/10.13182/NT78-A32118
Response of Oxide Fuel to Simulated Thermal Transients
G. Bandyopadhyay
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 349-358
Technical Paper | Fuel | doi.org/10.13182/NT78-A32119
Tensile Properties and Annealing Characteristics of H. B. Robinson Spent Fuel Cladding
A. A. Bauer, L. M. Lowry
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 359-372
Technical Paper | Fuel | doi.org/10.13182/NT78-A32120
Microstructures and Leachability of Vitrified Radioactive Wastes
W. N. Rankin, J. A. Kelley
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 373-380
Technical Paper | Radioactive Waste | doi.org/10.13182/NT78-A32121
A Generic Hazard Evaluation of Low-Level Waste Burial Grounds
B. L. Cohen, H. N. Jow
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 381-388
Technical Paper | Radioactive Waste | doi.org/10.13182/NT78-A32122
Minimizing Radioactivity and Other Features of Elemental and Isotopic Tailoring of Materials for Fusion Reactors
Robert W. Conn, Kevin Okula, A. Wayne Johnson
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 389-400
Technical Paper | Material | doi.org/10.13182/NT78-A32123
Application of Reactivity Weighting to Rod Ejection Accident Analysis in a Pressurized Water Reactor
S. Bian
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 401-407
Technical Note | Reactor | doi.org/10.13182/NT78-A32124
Swelling in Mixed-Oxide Fuel Pins
H. Zimmermann
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 408-410
Technical Note | Fuel | doi.org/10.13182/NT78-A32125
A Low-Decontamination Approach to a Proliferation-Resistant Fuel Cycle
J. G. Asquith, L. F. Grantham
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 137-148
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Fuel Cycle | doi.org/10.13182/NT78-A32100
Coprocessing—An Evaluation of Chemical Reprocessing Without Plutonium Separation
Meyer Pobereskin, Kenneth D. Kok, William J. Madia
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 149-167
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Fuel Cycle | doi.org/10.13182/NT78-A32101
Some Plutonium Recycle Program Fuel Cycles Having Reduced Proliferation Characteristics
Eugene A. Eschbach
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 168-179
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Fuel Cycle | doi.org/10.13182/NT78-A32102
An Investigation of Altered Transverse Transport of Axial Momentum in Coolant Flows During Oscillatory Instabilities
R. P. Roy, P. K. Jain
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 180-184
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Reactor | doi.org/10.13182/NT78-A32103
Investigations of Anticipated Transients Without Reactor Scram and Other Selected Safety Devices
W. Ullrich, W. Frisch
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 185-194
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Reactor | doi.org/10.13182/NT78-A32104
Enrichment Zoning and Control Rod Programming for Reactivity and Power Shape Control
Constantine P. Tzanos
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 195-206
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Reactor | doi.org/10.13182/NT78-A32105
Benchmark Critical Experiments on High-Enriched Uranyl Nitrate Solution Systems
Robert E. Rothe, Inki Oh
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 207-225
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Fuel Cycle | doi.org/10.13182/NT78-A32106
A Calculational Study of Benchmark Critical Experiments on High-Enriched Uranyl Nitrate Solution Systems
Inki Oh, Robert E. Rothe
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 226-243
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Fuel Cycle | doi.org/10.13182/NT78-A32107
Uranium Requirements for Advanced Fuel Cycles in Expanding Nuclear Power Systems
S. Banerjee, H. Tamm
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 244-251
Technical Paper | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Fuel Cycle | doi.org/10.13182/NT78-A32108
Analyzing Containment Leakage from a Sodium Fire by the Response Surface Method
Lucy W. Person
Nuclear Technology | Volume 41 | Number 2 | December 1978 | Pages 252-256
Technical Note | Extraction of Energy From Nuclear Fuels Without Reprocessing to Separate Plutonium / Reactor | doi.org/10.13182/NT78-A32109
