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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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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.
P. E. Reagan, R. L. Beatty, E. L. Long, Jr.
Nuclear Science and Engineering | Volume 28 | Number 1 | April 1967 | Pages 34-41
Technical Paper | doi.org/10.13182/NSE67-A18664
Articles are hosted by Taylor and Francis Online.
Fuel particles coated with pyrolytic carbon are contemplated for use in several high-temperature gas-cooled reactors. This paper describes the performance of pyrolytic carbon-coated, high-density, uranium oxide particles irradiated at 1300 to 1600°C. The fission-gas release, burnups, and temperatures for five experiments are given. Coated particles with a builtin gap between the fuel and the inner laminar coating began to show evidence of failure by releasing bursts of fission gas after 27.9% uranium burnup, and postirradiation examination revealed delamination of the inner coating. Coated particles made with a porous carbon buffer layer between the fuel and an isotropic coating showed no evidence of failure by fission-gas release, and showed no damage due to irradiation when examined by metallography. Coated particles with neither gap nor buffer, but with a low-density inner coating applied directly to the fuel, retained fission gas successfully but showed enlargement of cracks that had formed at the fuel-coating interface during the coating process. The oxide particles did not flow at high burnup and expand into voids and cracks as the carbide particles did, and the oxide did not diffuse into the carbon coating at high temperatures.