ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
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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August 2024
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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.
D. L. Dunaway, G. P. Miller, W. A. Johnson
Nuclear Technology | Volume 8 | Number 6 | June 1970 | Pages 482-487
Fuel Cycle | doi.org/10.13182/NT70-A28647
Articles are hosted by Taylor and Francis Online.
A study was initiated to determine the highest 235U enrichment that could be processed safely in a facility originally designed for refining natural uranium ores and concentrates. The equipment used in converting uranyl nitrate to uranium trioxide was determined to be the limiting factor. Calculations of neutron multiplication throughout the denitration cycle were made using data from the analysis of process material. It was determined that the maximum 235U enrichment could be safely increased to 2.0% from the previous limit of 1.25% 235U. Processing at the higher enrichment required slight changes in equipment to ensure against moderation of the material.
