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Division Spotlight
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.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Latest News
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
Donald L. Smith, Manuel M. Bretscher, J. W. Meadows
Nuclear Science and Engineering | Volume 78 | Number 4 | August 1981 | Pages 359-369
Technical Paper | doi.org/10.13182/NSE81-A21369
Articles are hosted by Taylor and Francis Online.
Cross sections for the 7Li(n,n't)4He reaction have been measured in the 7- to 9-MeV energy range. The tritium produced in encapsulated lithium metal samples by fast neutron bombardment was extracted and the activity measured using liquid scintillation counting techniques. The neutron fluence was measured with an ion chamber containing a 238U deposit. This deposit was calibrated by comparing it with standard 235U deposits. As a result, the error in the (n,n't) cross section is insensitive to the 238U fission cross-section error but does depend directly on the error in the 235U fission cross section. The experimental results show that the 7Li(n,n't)4He cross section is very insensitive to neutron energy in the 7- to 9-MeV range, and the value 372 mb (±3.8%) was obtained for the average cross section in this region.