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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
L. A. Lawrence, D. C. Hata, J. W. Weber
Nuclear Technology | Volume 42 | Number 2 | February 1979 | Pages 195-206
Technical Paper | Thorium Fuel Cycle in a Breeder Economy / Material | doi.org/10.13182/NT79-A32150
Articles are hosted by Taylor and Francis Online.
A significant reduction in and a change in the character of fuel-cladding chemical interaction (FCCI) due to a reduction in the oxygen-to-metal ratio (O/M) was established for uranium-plutonium mixed-oxide fuels clad with 20% cold-worked Type 316 stainless steel irradiated in the Experimental Breeder Reactor II. Fuel pins from the Hanford Engineering Development Laboratory P-23C subassembly at initial fuel O/Ms of 1.94, 1.95, and 1.97 were examined at peak burnups of 1.1, 2.5, and 3.6 at.%. The depth of FCCI increased with increasing burnup and temperature, but the relative effects of fuel O/M did not change. An approximate three-fold reduction in FCCI resulted from a reduction in fuel O/M from 1.97 to 1.95 at ∼3.6 at.%) burnup. The peak FCCI in the lower O/M fuel was ∼5 μm and appeared as a preferential loss of cladding at grain boundaries and slip planes on the cladding inner surface. In contrast, the typical FCCI in the higher O/M (1.97) fuel pin was matrix in character, and penetrated ∼14 μm into the cladding. Thus, FCCI in mixed-oxide fuel can be reduced to negligible levels by lowering the O/M during manufacture of the fuel.