ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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February 2025
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January 2025
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Latest News
Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
S. I. Bhuiyan, F. U. Ahmed, A. S. Mollah, M. A. Rahman
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 357-361
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT91-A34529
Articles are hosted by Taylor and Francis Online.
The neutron shielding properties of ilmenite-magnetite (I-M) concrete are measured experimentally. The instantaneous relaxation length and thickness-dependent removal cross section of neutrons from a 252Cf source penetrating I-M concrete with and without a cadmium sheet are reported. An empirical formula is developed to calculate the thickness dependence of the removal cross section and the related coefficients are reported. The results illustrate the effectiveness of I-M concrete so far as its shielding properties are concerned. This material can be used to shield reactors, accelerators, X-ray installations, and radioactive sources used for commercial purposes.
