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
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
January 2026
Nuclear Technology
December 2025
Fusion Science and Technology
November 2025
Latest News
AI at work: Southern Nuclear’s adoption of Copilot agents drives fleet forward
Southern Nuclear is leading the charge in artificial intelligence integration, with employee-developed applications driving efficiencies in maintenance, operations, safety, and performance.
The tools span all roles within the company, with thousands of documented uses throughout the fleet, including improved maintenance efficiency, risk awareness in maintenance activities, and better-informed decision-making. The data-intensive process of preparing for and executing maintenance operations is streamlined by leveraging AI to put the right information at the fingertips for maintenance leaders, planners, schedulers, engineers, and technicians.
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.
