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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
National Meeting
2020 Winter Meeting and Nuclear Technology Expo
November 15–19, 2020
Chicago, IL|Chicago Marriott 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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July 2020
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June 2020
Fusion Science and Technology
April 2020
Latest News
NEA issues call to action in report on nuclear cost reductions
A new report from the Paris-based OECD Nuclear Energy Agency declares that nuclear power is needed for countries to meet their Paris Agreement decarbonization and energy security policy goals, but that governmental support for a rapid reduction in the cost of new nuclear capacity through the creation of certain policy frameworks is likely necessary.
H. H. Toudeshki, C. J. Martin, F. Najmabadi, J. P. Blanchard
Fusion Science and Technology | Volume 68 | Number 3 | October 2015 | Pages 535-540
Technical Paper | Proceedings of TOFE-2014 | dx.doi.org/10.13182/FST15-112
Articles are hosted by Taylor and Francis Online.
ARIES ACT-1 is a conceptual design for a commercial tokamak with aggressive physics and engineering. In the spirit of advanced engineering, the vacuum vessel design employed several novel concepts. It eliminates the use of water cooling in order to allow higher temperature operation and reduce the tritium inventory. It employs a low activation bainitic steel that eliminates the need for post-weld heat treatment. It includes sufficient volume to accommodate a full loss of coolant accident. Finally, it employs a novel mechanical design in order to withstand the operating stresses during normal operation, anticipated transients, and disruptions. In this paper, we present the most recent design for this component, update the stress analysis confirming the suitability of the design, and present results for disruption forces due to a plasma quench.
