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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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IAEA to help monitor plastic pollution in the Galapagos Islands
The International Atomic Energy Agency announced that its Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative has partnered with Ecuador’s Oceanographic Institute of the Navy (INOCAR) and Polytechnic School of the Coast (ESPOL) to build microplastic monitoring and analytical capacity to address the growing threat of marine microplastic pollution in the Galapagos Islands.
Steven E. Skutnik, Man-Sung Yim
Nuclear Technology | Volume 179 | Number 3 | September 2012 | Pages 374-381
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A14169
Articles are hosted by Taylor and Francis Online.
The effect of simplifications in nuclear fuel depletion analysis as well as the effect of cross-section uncertainties were evaluated as to their impact upon material attractiveness for weapons diversion purposes. The effect of simplified depletion models for material attractiveness evaluation was evaluated through a comparison of pressurized water reactor fuel for several benchmark cases, using experimentally measured values along with a two-dimensional lattice physics model (TRITON) and a point depletion model (ORIGEN-S). Simplifications such as the use of the ORIGEN-S depletion libraries and assumptions of homogeneous core enrichment were found to have a negligible impact on material attractiveness evaluation, particularly relative to uncertainties in experimental measurements; additionally, simplified irradiation power histories do not introduce unacceptable errors into the attractiveness evaluation. Finally, the overall sensitivity of material attractiveness and associated uncertainty was found to be greater for transuranic mixtures compared to plutonium as a function of both burnup and decay time; however, associated uncertainties are generally small and not prohibitive to material attractiveness discrimination. As a result, the use of simplified depletion models such as ORIGEN-S appears to be well justified for use in material attractiveness evaluation for proliferation resistance studies.