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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
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.
J. Sanz, J.M. Perlado, D. Guerra, A.S. Pérez
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2009-2016
Safety, Recycling, and Waste Management | doi.org/10.13182/FST92-A30016
Articles are hosted by Taylor and Francis Online.
The primary objective is to develop information associated with waste production and management in ICF reactors to guide material selection for first structural walls (FSW). The capability to perform hands-on and remote recycling, and near-surface burial (NSB) of wastes is analyzed. Elemental concentration limits that would allow attainment of these objectives are calculated, and the performance of some candidate structural materials explored. Results indicate that some elements/impurities, should be restricted to levels below 1 ppm to meet requirements for NSB and hands-on recycling. Vanadium-based alloys and specially SiC present an excellent behaviour for waste management, whilst the development of steels with suitable activation characteristics is likely not to be feasible. The effect of energy spectrum and neutron fluence is also discussed.