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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
Cecilia Martin-del-Campo, Juan Luis François, Alejandra M. Barragan, Miguel A. Palomera
Nuclear Technology | Volume 157 | Number 3 | March 2007 | Pages 251-260
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT07-A3816
Articles are hosted by Taylor and Francis Online.
Construction of a fuzzy inference system for describing the objective function in a fuel lattice composition optimization problem is proposed. This technique allows for incorporating human expertise in searching for the best radial fuel enrichment and gadolinia distributions in a typical boiling water reactor fuel lattice. The optimization procedure adopted is a modified tabu search algorithm. Evaluation parameters included in the objective function are obtained by the neutronic lattice simulator HELIOS. The performance of the new objective function is compared to the objective function consisting in a single sum of individual objectives pondered by weighting factors. Results show that the fuzzy inference system performs very well for modeling the objective function in order to qualify the investigated solutions in a fuel composition lattice optimization process based on tabu search. The best solution found is a lattice with the desired neutronic characteristic.
