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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.
Zs. Németh, Á. Veres, I. Pavlicsek, L. Lakosi
Nuclear Science and Engineering | Volume 105 | Number 3 | July 1990 | Pages 233-243
Technical Paper | doi.org/10.13182/NSE90-A19188
Articles are hosted by Taylor and Francis Online.
New nondestructive methods for determining burnup and fissile content are introduced. Indium-115 is activated to metastable state by hard gamma rays of a spent-fuel assembly, where the isomer activity produced is proportional to the fissile content. The application of a beryllium converter increases sensitivity by nearly two orders of magnitude and also reduces the time needed. Alternative or simultaneous detection of neutrons emitted by the spent fuel is also available: The produced 116mIn activity is a function of burnup. Principles are verified by many experiments on WWR-SM assemblies. Axial and azimuthal gamma-ray and neutron profiles are also recorded to demonstrate the ability of the methods to detect burnup inhomogeneities. The advantages of the methods and the choice of target material are discussed. Applications for safeguards purposes are suggested.