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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
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.