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The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Latest News
From South Korea to Belgium: Testing a high-density research reactor fuel
The Korea Atomic Energy Research Institute has developed a high-density uranium silicide fuel designed to replace high-enriched uranium in research reactors. Recent irradiation tests appear to be successful, KAERI reports, which means the fuel could be commercialized to continue a key global nuclear nonproliferation effort—converting research reactors to run on low-enriched uranium fuel.
Lester M. Waganer, Richard J. Peipert, Jr., Xueren R. Wang, Siegfried Malang, ARIES Team
Fusion Science and Technology | Volume 54 | Number 3 | October 2008 | Pages 787-817
Technical Paper | Aries-Cs Special Issue | doi.org/10.13182/FST08-A1904
Articles are hosted by Taylor and Francis Online.
The goal of the ARIES compact stellarator is to define and assess a stellarator-based fusion power plant to provide electrical power as competitively as possible by balancing performance, cost, and plant availability. The traditional stellarator concepts are as compact as possible to reduce the plant capital costs, which are driven by the power core volume, weight, and cost. Different coil configurations are defined and assessed, trading plasma performance, power core design, access between the coils, and overall capital cost. Maintenance options are assessed and the port maintenance of first-wall/blanket and divertor modules is selected as the most feasible approach. Maintenance access is very important because the plasma-facing components have a limited lifetime. The available port access areas between the coils determine the maximum module envelope. With the maintenance approach selected, the frequency of maintenance determined, and module size defined, features of the maintenance approach are developed to maximize the power plant availability. After the preliminary maintenance approach, details for the power core components and facilities are finalized and a maintenance assessment is developed by analyzing the nominal times to conduct the maintenance actions. It is estimated that the ARIES-CS plant availability could reasonably be in the range of 85%.