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Division Spotlight
Education, Training & Workforce Development
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.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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.
Manfred Roedig, Reiner Duwe, Jochen Linke, Guenther Pott, Bernhard Wiechers
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 464-468
Plasma Facing Components Technology | doi.org/10.13182/FST98-A11963656
Articles are hosted by Taylor and Francis Online.
In order to study degradation effects of neutrons on plasma-facing materials and joints, actively-cooled beryllium and CFC samples were irradiated in the High Flux Reactor in Petten up to 0.35 dpa at 350 and 700°C. Later, these samples were tested by means of an electron beam facility under static and cyclic heating conditions. The heat removal efficiency and the thermal fatigue behavior of these samples were compared to those of corresponding non-irradiated samples. A significant increase of surface temperature was observed for all samples, due to a reduced thermal conductivity of the CFC materials after neutron irradiation. This effect is less distinctive for samples irradiated at the higher temperature. Long term fatigue tests with 1000 heating cycles at 15 MW/m2 did not create any failure of the plasma-facing material or the bond layer of the tested mock-ups. Similar experiments have been performed with brazed beryllium-copper mock-ups. Flat tile mock-ups with an S65 C armor on a CuCrZr heat sink were loaded up to 1000 cycles at a power density of 7 MW/m2 without detachment of tiles.