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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
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.