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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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Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
Reboot: Nuclear needs a success . . . anywhere
The media have gleefully resurrected the language of a past nuclear renaissance. Beyond the hype and PR, many people in the nuclear community are taking a more measured view of conditions that could lead to new construction: data center demand, the proliferation of new reactor designs and start-ups, and the sudden ascendance of nuclear energy as the power source everyone wants—or wants to talk about.
Once built, large nuclear reactors can provide clean power for at least 80 years—outlasting 10 to 20 presidential administrations. Smaller reactors can provide heat and power outputs tailored to an end user’s needs. With all the new attention, are we any closer to getting past persistent supply chain and workforce issues and building these new plants? And what will the election of Donald Trump to a second term as president mean for nuclear?
As usual, there are more questions than answers, and most come down to money. Several developers are engaging with the Nuclear Regulatory Commission or have already applied for a license, certification, or permit. But designs without paying customers won’t get built. So where are the customers, and what will it take for them to commit?
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Timing the Utilization of Recycle Fuels in High-Temperature Gas-Cooled Reactors
F. J. Homan
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 5-15
Technical Paper | Fuel Cycle | doi.org/10.13182/NT74-A31375
Application of Amberlite Xe-270 Resin to Purification of Neptunium
Wallace W. Schulz
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 16-25
Technical Paper | Chemical Processing | doi.org/10.13182/NT74-A31376
A Comparison of Sphere-Pac and Pellet (U,Pu)O2 Fuel Pins in Low-Burnup Instrumented Irradiation Tests
R. B. Fitts, F. L. Miller
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 26-38
Technical Paper | Fuel | doi.org/10.13182/NT74-A31377
Tritium in Fusion Power Reactor Blankets
R. G. Hickman
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 39-49
Technical Paper | Material | doi.org/10.13182/NT74-A31378
Neutron Fluence and Atomic Displacement Rates for Graphite Irradiations
W. C. Morgan
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 50-56
Technical Paper | Material | doi.org/10.13182/NT74-A31379
Gamma Gauge for the Control of Interzone Layer in an Extraction Tower
E. Elias, Y. Segal, A. Notea
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 57-66
Technical Paper | Instrument | doi.org/10.13182/NT74-A31380
Intercomparison of Nonperturbing Techniques for Inferring the Reactivity of Fast Reactors
A. R. Buhl, J. C. Robinson, E. T. Tomlinson
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 67-74
Technical Paper | Technique | doi.org/10.13182/NT74-A31381
A New Carbon-Activity Meter for High-Temperature Sodium
W. E. Ruther, S. B. Skladzien, M. F. Roche, J. W. Allen
Nuclear Technology | Volume 21 | Number 1 | January 1974 | Pages 75-78
Technical Note | Instrument | doi.org/10.13182/NT74-A31382
An Optimal Nuclear Fuel Management Model for Fast Reactors
H. G. Stoll, R. A. Axford
Nuclear Technology | Volume 21 | Number 2 | February 1974 | Pages 85-98
Technical Paper | Reactor | doi.org/10.13182/NT74-A31365
Two Interesting Phenomena Observed in the Axial Power Distribution of a BWR
T. Shimooke
Nuclear Technology | Volume 21 | Number 2 | February 1974 | Pages 99-110
Technical Paper | Reactor | doi.org/10.13182/NT74-A31366
Deep Self-Burial of Radioactive Wastes by Rock-Melting Capsules
Stanley E. Logan
Nuclear Technology | Volume 21 | Number 2 | February 1974 | Pages 111-124
Technical Paper | Radioactive Waste | doi.org/10.13182/NT74-A31367
A Method for Detecting Fuel Cladding Penetration in LMFBRrs by Monitoring the Sodium Coolant for Iodine-135
N. R. Chellew, W. E. Miller, R. W. Kessie, C. C. McPheeters, P. A. Nelson
Nuclear Technology | Volume 21 | Number 2 | February 1974 | Pages 125-132
Technical Paper | Instrument | doi.org/10.13182/NT74-A31368
Measurements of UF6 Cylinders with Portable Instruments
R. B. Walton, T. D. Reilly, J. L. Parker, J. H. Menzel, E. D. Marshall, L. W. Fields
Nuclear Technology | Volume 21 | Number 2 | February 1974 | Pages 133-148
Technical Paper | Instrument | doi.org/10.13182/NT74-A31369
Detection of Defective SiC Layers in Coated Nuclear Fuel Particles
D. M. Hewette, II, W. R. Laing
Nuclear Technology | Volume 21 | Number 2 | February 1974 | Pages 149-150
Technical Note | Fuel | doi.org/10.13182/NT74-A31370
Definitions of Breeding Ratio and Doubling Time
Harvey L. Wyckoff, Paul Greebler
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 158-164
Technical Paper | Reactor | doi.org/10.13182/NT74-A31387
Practical Xenon Spatial Control
Douglas C. Bauer, Claude G. Poncelet
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 165-189
Technical Paper | Reactor | doi.org/10.13182/NT74-A31388
Civil Defense Implications of an LMFBR in a Thermonuclear Target Area
C. V. Chester, R. O. Chester
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 190-200
Technical Paper | Reactor Siting | doi.org/10.13182/NT74-A31389
Two Fusion Reactor Blankets with Vanadium as Structural Material
James E. Struve, Nick Tsoulfanidis
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 201-207
Technical Paper | Material | doi.org/10.13182/NT74-A31390
In-Pile Thermal Conductivity of Fuel Oxide: UO2 Pellets and Vipac UO2-PuO2 Pellets and Sol-Gel
A. Calza-Bini, G. Cosoli, G. Filacchioni, M. Lanchi, A. Nobili, U. Rocca, P. L. Rotoloni
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 208-216
Technical Paper | Material | doi.org/10.13182/NT74-A31391
Calibration Stability of Oxygen Meters for LMFBR Sodium Systems
J. M. McKee, D. R. Vissers, P. A. Nelson, B. R. Grundy, E. Berkey, G. R. Taylor
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 217-227
Technical Paper | Material | doi.org/10.13182/NT74-A31392
The Utilization of On-Line Monitors at EBR-II for Sodium Purity
John T. Holmes, Grant O. Haroldsen
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 228-234
Technical Paper | Instrument | doi.org/10.13182/NT74-A31393
A Hydrogen-Activity Meter for Liquid Sodium and its Application to Hydrogen Solubility Measurements
D. R. Vissers, J. T. Holmes, L. G. Bartholme, P. A. Nelson
Nuclear Technology | Volume 21 | Number 3 | March 1974 | Pages 235-244
Technical Paper | Instrument | doi.org/10.13182/NT74-A31394
