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Division Spotlight
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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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.