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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
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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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Nicholas Tsoulfanidis—ANS member since 1969
We welcome ANS members who have careered in the community to submit their own Nuclear Legacy stories, so that the personal history of nuclear power can be captured. For information on submitting your stories, contact nucnews@ans.org.
As an undergraduate I studied physics at the University of Athens. I entered the university in 1955 after successfully passing a national exam (came up fourth in a field of about 700 candidates). Upon graduation and finishing my mandatory two-year military service, the plan was to teach physics either in a public high school or as a tutor for a private for-profit institution, preparing high school students for the national exam.
U. Samm
Fusion Science and Technology | Volume 57 | Number 2 | February 2010 | Pages 241-246
Edge Physics and Plasma-Wall Interactions | Proceedings of the Ninth Carolus Magnus Summer School on Plasma and Fusion Energy Physics | doi.org/10.13182/FST10-A9415
Articles are hosted by Taylor and Francis Online.
The control of wall loads in fusion devices, in particular with respect to the life time limitations of wall components due to material erosion and migration, will be decisive for the realisation of a fusion power plant operating in steady state, while in a pulsed experiment like ITER the primary goal for plasma-wall interaction is the achievement of a high availability. The article describes the grand challenges of plasma-wall interaction research along the needs for ITER and the strategies of ongoing research for further optimization of the design. Addressed are questions related to material limitations, erosion- and transport processes, tritium retention in deposited layers and transient heat loads.