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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
G. Karsten, G. Mühling, H. Plitz
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 208-215
Technical Paper | Fuel | doi.org/10.13182/NT76-A31561
Articles are hosted by Taylor and Francis Online.
The carbide fuel which will be introduced into the SNR for the first time after 1980, will be helium bonded, with a low linear heat rating and fuel density. This design appears to be the least problematic one for a medium burnup goal. The restriction to a moderate design arises to a certain extent from economical and safety reasons, but mainly can be attributed to uncertainties in extrapolation to a very high performance level. This can be demonstrated in a general discussion valid for both oxide and carbide. Due to the fact that the fuel elements of a large power plant with a peak burnup of 100 MWd/kg will undergo radiation damages, which cannot be demonstrated by experimental fuel pins in test (DFR, Rapsodie) or demonstration reactors (SNR, PFR, etc.) for the first generation, licensable maximum burnups will be in the range of 70 MWd/kg. It is impossible to perform tests outside the future large power plants with a relevant neutron dose-to-fuel burnup ratio. Therefore, in the German program a continuous development has been underway since 1968, in which separate medium burnups and neutron doses are demonstrated in test and demonstration reactors. In addition, the fuel fabrication process will be steadily improved in a pilot fabrication plant.