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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
G. Bandyopadhyay
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 349-358
Technical Paper | Fuel | doi.org/10.13182/NT78-A32119
Articles are hosted by Taylor and Francis Online.
Direct electrical heating (DEH) experiments have been analyzed to study the fuel and fission gas response to simulated thermal transient conditions in unirradiated UO2 and irradiated mixed-oxide fuels. The results indicate that both fission gas and fuel melting strongly influence the fuel response behavior during transients. The information obtained from the DEH tests has been used to draw a preliminary “fuel response diagram” that contributes to an understanding of such macroscopic fuel behavior as gross fuel swelling and fuel failure as functions of the transient time and heating rate. A comparison of these test results and the trend depicted by the fuel response diagram with results obtained from experiments performed in the transient reactor test facility indicates that certain aspects of fuel behavior during transients can be reasonably simulated by the DEH technique.
