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Conference Spotlight
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.
Firooz Rufeh, Donald R. Olander and Thomas H. Pigford
Nuclear Science and Engineering | Volume 23 | Number 4 | December 1965 | Pages 335-338
Technical Paper | doi.org/10.13182/NSE65-A21069
Articles are hosted by Taylor and Francis Online.
A high-pressure furnace that operates up to 2000°C in the pressure range of 100 atm to 10−5 torr was designed and constructed to saturate UO2 powder of 4-µm average particle size with 4He. The powder was then dissolved in a fused salt in an induction chamber. The released 4He was mixed with a known quantity of 3He, and the mixture was analyzed with a mass spectrometer to determine the 4He: 3He ratio, hence the original mass of 4He in the sample. The solubility of He in UO2 at 1200 and 1300°C was found to be 6.71 × 10−4 and 3.23 × 10−4 cm3 (STP)/(g atm), respectively. It was also found that the He-UO2 system obeys Henry's law. From a plot of He concentration as a function of time, the diffusion coefficient at 1200 °C was estimated to be 1.5 × 10−13 cm2/sec.