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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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2025 ANS Annual Conference
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Chicago, IL|Chicago Marriott Downtown
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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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
I. V. Shikhovtsev et al.
Fusion Science and Technology | Volume 47 | Number 1 | January 2005 | Pages 321-323
Technical Paper | Open Magnetic Systems for Plasma Confinement | doi.org/10.13182/FST05-A677
Articles are hosted by Taylor and Francis Online.
A diagnostic neutral beam injector based on radiofrequency ion source has been developed at BINP, Novosibirsk for plasma diagnostics in magnetic fusion devices including magnetic mirrors with pulse duration up to several seconds, plasma density up to 1020 m-3 and plasma radius ~0.5m.It was observed that properties of the ceramic plasma box considerably changed after several hours of integrated operational time. After that, the proton specie in the beam essentially decreases. Eventually the proton component of the beam decreases approximately by 10% (from 60% down to 50% by current). This problem can be resolved by protection of the ceramic wall by a Faraday shield. We investigated the shield, which was made of aluminium tube with longitudinal slits and with a diameter close to that of the inner ceramic wall of the plasma box.This paper discusses the results of the beam composition measurements after installation of the Faraday shield.
