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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
D. Y. Hsia, P. Griffith
Nuclear Science and Engineering | Volume 78 | Number 4 | August 1981 | Pages 431-437
Technical Note | doi.org/10.13182/NSE81-A21380
Articles are hosted by Taylor and Francis Online.
Steam generator pressure drop versus flow rate instability during a loss-of-coolant accident in a pressurized water reactor has been investigated. The steam generator is simulated by four tubes, each with a different height, on top of a two-dimensional quarter-circle inlet plenum. This work deals with only an adiabatic air-water system. The pressure drop was found to be practically constant in the range of 3 jg 10 m/s. Within this range, the pressure drop depends only on the liquid flow rate. The plenum details do not matter. A model using an average flow for each tube does a good job in estimating the pressure drop. The flow distribution can be conservatively estimated by the proposed model based on a single, average tube pressure drop minimum.
