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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
ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
R. B. Gordon
Nuclear Science and Engineering | Volume 3 | Number 3 | March 1958 | Pages 232-249
Technical Paper | doi.org/10.13182/NSE58-A25464
Articles are hosted by Taylor and Francis Online.
To achieve adequate corrosion resistance in high-temperature water, the chemical composition and fabrication of zirconium cladding material must be carefully controlled. Present technology permits the satisfactory fabrication of a variety of fuel materials which are compatible with zirconium cladding. Homogeneity and melting crucible problems still exist with some of the fuel alloys. Zirconium-clad fuel elements of the bonded type are produced by pack rolling or coextrusion of the fuel and cladding. The optimum working temperature represents a balance between the need for minimizing differences in plasticity between fuel and cladding and for adequate diffusion at the clad-fuel interface. Unbonded fuel elements require close dimensional control of fuel and cladding and high-quality closure welds which are made possible by the excellent welding characteristics of Zircaloy.