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.
Explore membership for yourself or for your organization.
Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
October 2025
Nuclear Technology
September 2025
Fusion Science and Technology
Latest News
ANS continues to expand its certificate offerings
It’s almost been a full year since the American Nuclear Society held its inaugural section of Nuclear 101, a comprehensive certificate course on the basics of the nuclear field. Offered at the 2024 ANS Winter Conference and Expo, that first sold-out course marked a massive milestone in the Society’s expanding work in professional development and certification.
C. R. Weisbin, R. H. Augustson, J. S. Hendricks, A. E. Evans, G. D. Turner, K. D. Böhnel
Nuclear Technology | Volume 15 | Number 3 | September 1972 | Pages 455-461
Technical Paper | Analysis | doi.org/10.13182/NT72-A16042
Articles are hosted by Taylor and Francis Online.
The total 235U content of low enrichment power reactor fuel assemblies has been determined by interrogation with Li(p,n) neutrons (200 to 500 keV) produced by a Van de Graaff proton accelerator and by measurement of fission-induced delayed neutrons. To extend the application of this assay technique and to optimize its implementation, numerical calculations have been performed using a modified Monte Carlo approach. Experimental measurements from a BWR-type fuel assembly have verified the mathematical model employed. By incorporating results from both calculation and measurement, a system is being designed to assay the total 235U content of power reactor fuel elements with an overall uncertainty within 2%. Using commercially available fuel handling equipment, the analysis time for the entire element is estimated to be ∼30 min.
