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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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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.
G. L. Kulcinski, J. P. Blanchard, G. A. Emmert, L. A. El-Guebaly, H. Khater, C. W. Maynard, E. A. Mogahed, J. E Santarius, M. E. Sawan, I. N. Sviatoslavsky, L. J. Wittenberg
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1779-1783
Alternate Concept and Application | doi.org/10.13182/FST92-A29978
Articles are hosted by Taylor and Francis Online.
A comparison of the key features of the D-3He Apollo and the DT Aries fusion power reactor designs is made. The reduction in neutron production from the D-3He reaction has a major effect on the performance of Tokamak reactors. One of the biggest impacts is the low radiation damage rate in D-3He systems which allows a permanent first wall to be utilized.. The reduction in radioactivity in D-3He reactors has a particularly advantageous effect on the storage of wastes as well as on the safety to the public in the event of the worst conceivable accident. The more difficult D-3He physics requirements are offset by the technological advantages of using this fuel in place of the DT cycle.