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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.
Meeting Spotlight
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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Nuclear Technology
Fusion Science and Technology
Latest News
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.
M. Zucchetti, B. Coppi
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2017-2022
Safety, Recycling, and Waste Management | doi.org/10.13182/FST92-A30017
Articles are hosted by Taylor and Francis Online.
A study on the activation of the Ignitor machine is performed. The machine has been modelled with the neutron transport code ANISN, in orderto calculate the neutron fluxes. These have been input in the inventory code ANITA, and the neutron-induced radioactivity in the structures of the machine is obtained. It becomes clear that the activation of certain parts of the machine (vessel, magnets) requires the adoption of remote handling equipment for their maintenance. The substitution of INCONEL 625 (vessel material for Ignitor) by a material with lower long-term activation is discussed.
