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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Site acquired for GLE laser enrichment plant
Global Laser Enrichment (GLE) has acquired a 665-acre parcel of land for its planned Paducah Laser Enrichment Facility (PLEF) in Kentucky.
E. R. Hodgson
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 89-96
Diagnostics | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14118
Articles are hosted by Taylor and Francis Online.
Present ITER diagnostics are designed to provide machine protection, basic and advanced control, fusion performance evaluation, and an extensive measurement capability for furthering plasma physics understanding. However, in the longer term beyond ITER, diagnostic components and associated materials must survive extended periods in the more hostile environment of not only DEMO, but also fusion power plants. In addition to the need to minimize penetrations in the first wall, undoubtedly due to their known high sensitivity to radiation, the use of insulators, and hence diagnostics, will be further severely restricted to those essential to operation, safety, and maintenance related to plasma control and machine protection. The problems we will have to address are related to long-term fluence or dose-related degradation of the required properties due to aggregation and segregation of radiation-induced defects and impurities present in the original materials, as well as H, He, and other transmutation elements. To resolve these challenges, long-term research activities must increase. For the diagnostics (and other systems), in situ irradiation testing is essential. In the near- to mid-term future, available experimental fission reactors will be invaluable, where even basic problems such as irradiation in vacuum and temperature control must be overcome.