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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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November 2024
Latest News
Texas-based WCS chosen to manage U.S.-generated mercury
A five-year, $17.8 million contract has been awarded to Waste Control Specialists for the long-term management and storage of elemental mercury, the Department of Energy’s Office of Environmental Management announced on November 21.
A. R. Raffray, F. Escourbiac, F. J. Fuentes, L. Giancarli, B. Macklin, A. Martin, M. Merola, R. Mitteau, J. Palmer
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 465-476
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-945
Articles are hosted by Taylor and Francis Online.
The overall programmatic objective of ITER is to demonstrate the scientific and technological feasibility of fusion energy for peaceful purposes. The physics part of this objective (including burning plasma, Q of at least 10 and stationary conditions) seems to be well appreciated by the scientific community internationally. However, there seems to be less of an emphasis on the fusion technology part of the objective, which includes demonstrating the availability and integration of technologies essential for a fusion reactor and testing components including tritium breeding blanket modules for a future reactor. In fact important technology information will be obtained from the design, fabrication and operation of the vacuum vessel and out-of-vessel systems such as magnets, tritium system, cryogenic systems, cooling water systems, and associated safety aspects. In addition, DEMO-relevant information will be obtained from the operation of breeding blanket test modules in ITER. Moreover valuable information applicable to DEMO and beyond will also be obtained in a number of areas linked to in-vessel components. This paper summarizes the DEMO-relevant fusion technology information that will be obtained from ITER with a major focus on the areas linked to in-vessel components.