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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.
W. R. Johnson, L. D. Thompson, Thomas A. Lechtenberg
Nuclear Technology | Volume 66 | Number 1 | July 1984 | Pages 88-101
A. Selection, Production, and Development of Alloys for HTGR Component | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33458
Articles are hosted by Taylor and Francis Online.
The utilization of the high-temperature gas-cooled reactor (HTGR) for advanced or process heat applications will require the use of wrought components operating at temperatures up to 1000°C (1832°F) for times approaching 30 yr. Alloys for such components must withstand the corrosive effects (carburization and oxidation) of the impure helium primary coolant environment and maintain adequate elevated temperature strength. Commercially available wrought alloys have been found to be seriously limited for such applications because of their inherently poor resistance to corrosion in impure helium. As one approach to the solution of this problem, a program has been initiated to develop wrought alloys having a better combination of corrosion resistance and high-temperature strength, under advanced HTGR conditions, than commercial alloys currently available. This program culminated in 1980 with the design, melting, and fabrication of ten experimental Ni-Cr-Mo-W-Al-Ti-Zr-C alloys and with the initiation of efforts to evaluate their corrosion and mechanical behavior. Results of tests showed that all the experimental alloys exhibited superior carburization resistance in advanced reactor helium. In addition, several of the alloys exhibited excellent mechanical properties, including, in the case of one alloy, creep rupture strength at 900°C (1652°F), significantly better than that of the commercial alloy Inconel-617.