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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Fusion Science and Technology
Latest News
Deep Space: The new frontier of radiation controls
In commercial nuclear power, there has always been a deliberate tension between the regulator and the utility owner. The regulator fundamentally exists to protect the worker, and the utility, to make a profit. It is a win-win balance.
From the U.S. nuclear industry has emerged a brilliantly successful occupational nuclear safety record—largely the result of an ALARA (as low as reasonably achievable) process that has driven exposure rates down to what only a decade ago would have been considered unthinkable. In the U.S. nuclear industry, the system has accomplished an excellent, nearly seamless process that succeeds to the benefit of both employee and utility owner.
M. S. Tillack, X. R. Wang, D. Navaei, H. H. Toudeshki, A. F. Rowcliffe, F. Najmabadi, ARIES Team
Fusion Science and Technology | Volume 67 | Number 1 | January 2015 | Pages 49-74
Technical Paper | doi.org/10.13182/FST14-790
Articles are hosted by Taylor and Francis Online.
ARIES-ACT1 is the latest in a series of tokamak power plant designs that capitalize on the high-temperature capabilities and attractive safety and environmental characteristics of SiC composites coupled with a self-cooled lead-lithium breeder. This combination offers both design simplicity and high performance, capable of operating at very high coolant outlet temperature in a moderately high-power-density device. Blankets are supported within a poloidally continuous He-cooled steel structural ring, which adds robustness and minimizes loads on the SiC modules. In order to withstand high local surface heat flux in the divertor (of the order of 14 MW/m2 time averaged), a helium-cooled tungsten-alloy divertor was adopted. About 25% of the total “high-grade” heat is thus removed by helium, to be combined with the blanket heat in order to feed the power cycle. In addition to the in-vessel power-producing elements of the design, this paper also summarizes the key features and analysis of the vacuum vessel and power conversion system.