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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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
K. Asatani, M. Shiotani, Y. Hattori
Nuclear Science and Engineering | Volume 62 | Number 1 | January 1977 | Pages 9-19
Technical Paper | doi.org/10.13182/NSE77-A26935
Articles are hosted by Taylor and Francis Online.
A new method based on the singular perturbation theory is presented for synthesizing suboptimal control of nuclear reactors with spatially distributed parameters. The inverse of the neutron velocity is regarded as a small perturbing parameter, and the model, adopted for simplicity, is an infinite slab reactor described by the one-group diffusion equation. A control is found for the problem of transferring a given distributed neutron flux to the desired one assuming the deviation is small. It is shown that the Helmholtz mode is suited for the singular perturbation technique when one carries out the modal expansion, and the mode controllability is then determined in view of the asymptotic stability of solutions, which depends on the criticality condition. The theoretical estimation of the error of solution is also attached. A numerical example is given showing a large saving of computation time in the present method.