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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.
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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
Framatome, KHNP to investigate producing Lu-177 in South Korea
Framatome and Korea Hydro & Nuclear Power (KHNP) announced the signing of a memorandum of understanding to explore the possibility of producing the medical isotope Lutetium-177 at KHNP’s Wolsong nuclear power plant in South Korea. The companies also will investigate the feasibility of using the plant to support Korean production of medical radioisotopes in the future.
Yu. Igitkhanov, B. Bazylev, I. Landman
Fusion Science and Technology | Volume 64 | Number 2 | August 2013 | Pages 245-249
Plasma-Material Interactions | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 1), Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST13-A18084
Articles are hosted by Taylor and Francis Online.
In the steady-state operation the life-time performance of functional and structural materials in fusion reactor DEMO will be limited by several processes such as a sputtering erosion, transient events and neutron irradiation. The design strategy is to determine the structure and coating thicknesses which maximize component lifetime against all lifetime limitations. The sputtering erosion of the first wall tungsten armor layer due to the plasma impact during the steady state DEMO operation is considered here. It is shown that for DEMO conditions the total sputtering erosion of W armor by the charge-exchange DT neutrals could at least reach~1mm during one year of steady-state operation.