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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.
Man Gyun Na, Won Il Ko, Hangbok Choi
Nuclear Science and Engineering | Volume 142 | Number 3 | November 2002 | Pages 315-326
Technical Paper | doi.org/10.13182/NSE02-A2310
Articles are hosted by Taylor and Francis Online.
A combination method of spent pressurized water reactor (PWR) fuel is proposed that adjusts the fuel composition for direct use of spent PWR fuel in Canada deuterium uranium (CANDU) reactors (DUPIC). This method reduces the composition heterogeneity (variation) of the DUPIC fuel caused by directly reusing spent PWR fuel as DUPIC fuel feedstock. In this study, a combination method was used to find the optimum mixture composition from the spent PWR fuel database by minimizing the composition variation of the major fissile isotopes 235U and 239Pu. The simulation results have shown that the combination method can reduce the composition variation of 235U and 239Pu to 0.11 and 1.40%, respectively, through assemblywise mixing operation only. It is also believed that the result could be improved further through a rodwise combination technique if the isotopic composition of each spent PWR fuel rod is known by direct measurement during the DUPIC fuel fabrication process.
