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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
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.
John Sheffield, Mohamed Sawan
Fusion Science and Technology | Volume 53 | Number 3 | April 2008 | Pages 780-788
Technical Paper | doi.org/10.13182/FST53-780
Articles are hosted by Taylor and Francis Online.
Catalyzed D-D is the ultimate fusion cycle, because deuterium is essentially unlimited on earth. In this approach, the 3He and tritium fusion products are recycled to increase the charged particle fusion power. A difficulty with this fusion cycle is that the tritium from fusion, if left in the plasma, produces 14-MeV neutrons, leading to radiation damage comparable to that of the D-T cycle. This paper shows that the damage problems may be alleviated by removing tritium before it can burn. Fortunately, the charged particle fusion power from burning the tritium is small compared to that from the 3He and removing it from the plasma makes little difference to the plasma power balance. Ion cyclotron power might be used to pump out tritium. In this paper, we review the benefits of tritium removal, identify the issues associated with this approach, and determine illustrative parameters required for an advanced tokamak and an advanced stellarator.