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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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
ORAU, ANS, others to host workshops on nuclear academic programs
Oak Ridge Associated Universities (ORAU), in partnership with the American Nuclear Society, the Nuclear Energy Institute, and the Institute for Nuclear Power Operators, has announced it will host an online workshop called “Shaping the Future of Nuclear Academic Programs.” The 90-minute program is designed for university department heads and faculty interested in enhancing nuclear science and technology programs through best practices.
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.