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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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NEI chief executive highlights “unlimited potential” for nuclear in state of the industry address
Korsnick
In the Nuclear Energy Institute’s annual State of the Nuclear Energy Industry report, NEI president and CEO and Maria Korsnick expressed optimism about the nuclear industry and she issued a call to action.
Her address was part of NEI’s Nuclear Energy Policy forum. The forum, being held in Washington, D.C., on May 20 and May 21, brings together industry leaders, policy stakeholders, and clean energy experts to discuss nuclear advocacy. Korsnick’s remarks focused on the private capital flowing into the industry, progress on regulatory reform and new nuclear technology, and how the U.S. is trying to take the lead on the global nuclear stage.
“We are here at an unprecedented time in our industry history,” Korsnick said. “I’m proud to say that the nuclear industry has a future of unlimited potential.”
P. J. Fehrenbach, P. A. Morel, R. D. Sage
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 112-119
Technical Paper | Material | doi.org/10.13182/NT82-A32886
Articles are hosted by Taylor and Francis Online.
Measurement of fuel element diameters while the fuel is operating at power, in-reactor, has provided evidence of in-reactor fuel densification and relocation. The design and operation of the in-reactor diameter measuring rig used for these measurements are described. Diameter measurements were obtained from two fresh Zircaloy-clad UO2 elements containing fuel of 10.64 and 10.82 Mg/m3 density, respectively, at linear power outputs up to 61 kW/m. Similar measurements were also obtained from a 10.64 Mg/m3 density element after low power irradiation at 26 kW/m to a burnup of 75 MW- h/kg uranium. Results indicate that higher starting fuel density and prior irradiation both reduce the amount and rate of in-reactor fuel densification observed. Diameter measurements following reactor shutdowns, particularly on the higher burnup element, also indicate that fuel relocation can overcome diameter decreases due to fuel densification and restore pellet-clad interaction.
