ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
F. U. Ahmed, S. I. Bhuiyan, A. S. Mollah, M. M. Rahman
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 379-386
Technical Note | Radiation Protection | doi.org/10.13182/NT92-A34667
Articles are hosted by Taylor and Francis Online.
Gamma-ray shielding properties of ilmenite-magnetite (I-M) concrete and polyboron are measured with an NaI(Tl) detector. The detector response function is studied, and the inverted detector response matrix is generated. Using this inverted response matrix, the pulse-height spectra of gamma rays transmitted through the shields are converted into photon spectra, and the respective dose rates are calculated. The instantaneous relaxation lengths and the buildup factors for gamma rays from a 252Cf source penetrating I-M concrete and polyboron slabs are reported. Buildup factors and instantaneous relaxation lengths are fitted to the appropriate functions, and the related coefficients are also reported.
