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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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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.
Wolfgang Goll, Hans-Peter Fuchs, Reiner Manzel, Fritz U. Schlemmer
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 29-46
Technical Paper | Mixed-Oxide Fuel / Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34800
Articles are hosted by Taylor and Francis Online.
Recycling of plutonium in light water reactors in the Federal Republic of Germany began in 1966, and through the subsequent years, has reached a commercial state. Irradiation programs and postirradiation examinations (PIEs) of modern, highly soluble mixed-oxide (MOX) fuel of the ammonium uranyl plutonyl carbonate/optimized co-milling type have been carried out since 1981 to evaluate fuel performance and to verify the data base for design. The results of PIEs on MOX fuel rods with burnups ranging from 6 to 47 G Wd/tonne heavy metal are described. The dimensional behavior of the MOX fuel rods is found to be almost identical to that of UO2 fuel rods. Densification and swelling of MOX fuel are governed by the behavior of the UO2 matrix as well as the porosity that develops in the MOX agglomerates. Little uranium-plutonium interdiffusion occurs in MOX fuel irradiated under normal power reactor conditions, but substantial redistribution is found in the high-temperature region of transient-tested fuel. Fission gas release from the MOX agglomerates occurs via the UO2 matrix, resulting in release behavior similar to that of UO2 fuel. A comparison of the relevant physical properties of UO2 and MOX fuel shows that no distinct difference in the fission product release behavior of defective MOX fuel is to be expected. The available data base does not indicate any MOX-specific characteristic that could limit the burnup potential of this fuel compared with UO2 fuel.