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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.
Yassin A. Hassan, Omar Rais
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 77-86
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34569
Articles are hosted by Taylor and Francis Online.
The current version of the RELAP5/MOD2 computer code underpredicts the degree of superheat in the secondary side of the steam generator bundles. Many studies have concluded that this is due to overprediction of the interphase drag force. New interphase drag correlations have been developed for the bubbly and slug regimes. These correlations were implemented in the current version of the RELAP5/MOD2 computer code. Steady-state conditions for 65, 75, and 100% power loads of 30-tube once-through steam generator tests are simulated. The calculated primary- and secondary-side temperature profiles show that the new interphase drag correlations achieve closer agreement with experimental data than the temperature profiles of the original code.
