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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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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.
E. Sowa, J. Pavlik
Nuclear Technology | Volume 54 | Number 2 | August 1981 | Pages 234-238
Technical Note | Nuclear Safety | doi.org/10.13182/NT81-A32739
Articles are hosted by Taylor and Francis Online.
The possibility of a core meltdown during a hypothetical core disruptive accident may result in penetration at the bottom of the primary containment. As a consequence, core debris may be ejected from the reactor vessel and come in contact with the concrete or other refractory material located under the vessel. Decay heat will continue to be generated at this location. Small-scale experiments using thermite ignition followed by electrical heating have shown that solution and dilution of the UO2 fuel in the molten refractories take place. Experiments in concrete and zirconia at power levels of 5 to 6 to 24 to 46 W/g UO2 and exposure time varying from 6 to 55 min showed a typical behavior of melting and/or decomposition of the refractory along with formation of a compound melt. Eventual dilution reaches a temperature where solidification of the glass results in immobilization of core material.