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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island 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!
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Three nations, three ways to recycle plastic waste with nuclear technology
Plastic waste pollutes oceans, streams, and bloodstreams. Nations in Asia and the Pacific are working with the International Atomic Energy Agency through the Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative to tackle the problem. Launched in 2020, NUTEC Plastics is focused on using nuclear technology to both track the flow of microplastics and improve upstream plastic recycling before discarded plastic can enter the ecosystem. Irradiation could target hard-to-recycle plastics and the development of bio-based plastics, offering sustainable alternatives to conventional plastic products and building a “circular economy” for plastics, according to the IAEA.
E. Y. Lim, A. Leonard
Nuclear Science and Engineering | Volume 64 | Number 2 | October 1977 | Pages 694-708
Technical Paper | doi.org/10.13182/NSE77-A27401
Articles are hosted by Taylor and Francis Online.
A methodology is developed to determine the fuel pin enrichment distribution that yields the best approximation to a prescribed power distribution in boiling water reactor fuel bundles. Optimal pin enrichments are defined as those that minimize the sum of squared deviations between the actual and prescribed fuel pin powers. A constant average enrichment constraint is imposed to ensure that a suitable value of reactivity is present in the bundle. In the special case when each pin in the bundle is permitted to have a different enrichment value, the solution is obtained iteratively using a projected gradient algorithm. Gradient information and power distributions are computed by adapting the response matrix method to fuel bundle power calculations. In the general case when the fuel pins are limited to a few enrichment types, one obtains a combinatorial optimization problem. Formally, the assignment of an enrichment type to the various fuel pins is made through a matrix of Boolean variables. Since the optimal assignment, as well as the optimal values, of the enrichment types must be determined, a nonlinear mixed integer programming problem must be solved. Algorithms based on either exhaustive enumeration or branch and bound are shown to give a rigorous solution, but are computationally overwhelming. Solutions that require only moderate computational effort are obtained by assuming that the fuel pin enrichments in the combinatorial problem maintain the ordering that was found in the special case mentioned above. Search schemes using branch and bound now become computationally attractive. An adaptation of the Hooke-Jeeves pattern search technique is shown to be especially efficient.