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
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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June 2025
Nuclear Technology
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May 2025
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.
Peter Colombo, Robert M. Neilson, Jr.
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 30-38
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31735
Articles are hosted by Taylor and Francis Online.
Techniques are developed for the solidification of radioactive wastes in concrete. Included are the sources, storage, volume reduction, and solidification of liquid wastes at Brookhaven National Laboratory using the cement-vermiculite process, as well as solid waste treatment, shipping containers, and off-site shipments of solid wastes. The properties of low-heat-generating high-level wastes, simulating those in storage at the Savannah River Plant, solidified in concrete were determined. Polymer impregnation was found to further decrease the leachability and improve the durability of these concrete waste forms.