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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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.
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.
