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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.
Wolfgang Kastner, Gerd J. Seeberger
Nuclear Technology | Volume 60 | Number 2 | February 1983 | Pages 268-277
Technical Paper | Radiation Effects and Their Relationship to Geological Repository / Fission Reactor | doi.org/10.13182/NT83-A33083
Articles are hosted by Taylor and Francis Online.
The impact of a loss-of-coolant accident (LOCA) on a nuclear reactor is determined in its first phase by many events, one of them being the behavior of the reactor coolant pumps. In this case, a mixture of steam and water flows through the pumps. Experiments were carried out to examine the family of characteristics of geometrically scaled pumps (scale 1:5 and 1:4) within the relevant parameter range under such conditions. The presented results of steady-state experiments are compared with results of former projects. Besides flow and speed, the most significant parameters on two-phase pump performance are void fraction and system pressure. A brief comparison between steady-state and transient results is provided. The impact of the pump’s behavior on the LOCA is demonstrated on the basis of blowdown calculations using various pump models and two-phase pump data.
