ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
2022 ANS Winter Meeting and Technology Expo
November 13–17, 2022
Phoenix, AZ|Arizona Grand 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!
Latest Magazine Issues
Sep 2022
Jul 2022
Latest Journal Issues
Nuclear Science and Engineering
October 2022
Nuclear Technology
Fusion Science and Technology
Latest News
The DRUM program: Cataloging America’s abandoned uranium mines
Based on a review of U.S. Atomic Energy Commission (AEC) records and available data from numerous agencies, there are an estimated 4,225 mines across the country that provided uranium ore to the U.S. government for defense-related purposes between 1947 and 1970. To aid in the cleanup of these legacy uranium mines and establish a record of their locations and current conditions, the Defense-Related Uranium Mines (DRUM) program was established within the Department of Energy’s Office of Legacy Management (LM).
Technical Session|Sponsored by Materials Science & Technology
Friday, April 15, 2022|1:15–2:45PM CDT|Loyalty Room
Sponsored by ANS Material Science & Technology Division
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Evaluation of Kanthal APMT as Potential Fuel Cladding Material
Arnold Pradhan (Univ. of Idaho)
Summary
Characterization of High Temperature Surrogate Cermet Fuel for Nuclear Thermal Propulsion (NTP)
James F. Mudd (Missouri Univ. Science and Technology)
Design Analysis of Accident-tolerant Cladding FeCrAl for Light Water Reactors
Rowan Marchie (Univ. Michigan), Henry Blackwood (Univ. Michigan), Jonathan Kurian (Univ. Michigan), Fei Gao (Univ. Michigan), Lumin Wang (Univ. Michigan)
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