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Conference Spotlight
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.
Yoshiyuki Inagaki, Kazuhiko Kunitomi, Yoshiaki Miyamoto, Ikuo Ioka, Kunihiko Suzuki
Nuclear Technology | Volume 99 | Number 1 | July 1992 | Pages 90-103
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34706
Articles are hosted by Taylor and Francis Online.
The high-temperature engineering test reactor (HTTR) is a 30-MW(thermal) helium gas-cooled reactor being constructed by the Japan Atomic Energy Research Establishment. A thermal mixing study of the coolant in the core bottom structure (CBS) of the HTTR is conducted to clarify the thermal-hydraulic characteristics of the coolant and estimate the influence of a hot streak on the intermediate heat exchanger (IHX) and a pressurized water cooler (PWC) downstream from the core. An experiment is carried out using an in-core structure test section (a full-scale simulation model of the CBS) of the helium engineering demonstration loop (HENDEL), and a numerical analysis is made using a three-dimensional time-dependent flow and heat transfer code including a k-ε model of turbulence. It is confirmed that the coolant is mixed sufficiently in the CBS and the outlet gas duct of the HTTR, and the hot streak had little effect on the IHX and the PWC.
