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May 31–June 3, 2026
Denver, CO|Sheraton Denver
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Latest News
Modernizing I&C for operations and maintenance, one phase at a time
The two reactors at Dominion Energy’s Surry plant are among the oldest in the U.S. nuclear fleet. Yet when the plant celebrated its 50th anniversary in 2023, staff could raise a toast to the future. Surry was one of the first plants to file a subsequent license renewal (SLR) application, and in May 2021, it became official: the plant was licensed to operate for a full 80 years, extending its reactors’ lifespans into 2052 and 2053.
Sehila M. Gonzalez De Vicente, Sergei Dudarev, Michael Rieth
Fusion Science and Technology | Volume 66 | Number 1 | July-August 2014 | Pages 38-45
Technical Paper | doi.org/10.13182/FST13-764
Articles are hosted by Taylor and Francis Online.
The Fusion Materials Topical Group (FMTG) coordinates, under the European Fusion Development Agreement (EFDA), the EU effort on the development of structural and protection materials for the very demanding operating conditions of a future DEMO reactor. The reference documents for this program are the European Roadmap for Fusion and the Materials Assessment Group (MAG) report. The FMTG work or EFDA work is structured as follows: a) Integrated radiation effects modelling and experimental validation: focused on the development of a conceptual and quantitative framework for the interpretation of experimental tests on steels and iron-based alloys and tungsten and tungsten alloys and predicting the performance of these materials under DEMO-relevant operating conditions. b) High heat flux materials: focused on the development of materials for armour applications (W alloys), structural applications for low and high temperature cooling concepts (Cu-based alloys, W-based alloys), materials technologies (joining, fabrication), and testing of prototype of cooling structures. c) Nano-structured oxide dispersion strengthened (ODS) ferritic steel development: focused on the development of an ODS ferritic steel with high tensile and creep strength and sufficient ductility and fracture toughness up to about 750°C, as well as good radiation resistance. d) Materials database status and needs for DEMO conceptual design activities: focused on the assessment and analysis of fusion materials available data, identifying areas of uncertainties and conditions (relevant to the design) where data are either missing or unreliable.