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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
Canada clears Darlington to produce Lu-177 and Y-90
The Canadian Nuclear Safety Commission has amended Ontario Power Generation’s power reactor operating license for Darlington nuclear power plant to authorize the production of the medical radioisotopes lutetium-177 and yttrium-90.
S. G. Durbin, C. W. Morrow, M. E. Kipp, D. L. Smith
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 465-469
IFE Drivers and Chambers | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8946
Articles are hosted by Taylor and Francis Online.
The ultimate goal of this research is to understand how the recyclable transmission lines (RTL) fail and break apart following each power generating pulse under inertial-fusion-energy-type loading. Containing and collecting the resulting dust, debris, and shrapnel so that it may be repetitively reprocessed and recycled is an especially important step, among many others, to successfully operating a power plant. In this paper the current and the dynamic pressure pulse along the RTL are simulated with the Micro-Cap network circuit code. These results are used as inputs to the CTH shock physics code that characterizes the debris formation and containment wall impacts. These models were applied to represent different sections of the RTL at two resolutions. The following discussion addresses the full size nested cone RTL for a Z-pinch IFE power plant.