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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.
B. S. Moon, K. R. Kim, J. S. Moon, S. B. Kim
Nuclear Science and Engineering | Volume 122 | Number 3 | March 1996 | Pages 417-422
Technical Paper | doi.org/10.13182/NSE96-A24176
Articles are hosted by Taylor and Francis Online.
Equipment that is one-tenth the size of the steam generators for the Westinghouse 900-MW(electric) nuclear power plants is used to study the swell and shrinkage of the water level. The cyclic aspect of level swell and shrinkage occurring during low-power operation of the nuclear power plants is realized by sequential steam dump valve control. Experimental results show that a simple mathematical model based on the amount of steam generated during depressurization provides a good approximation for predicting level swell and shrinkage. Steam generation also causes water movement between the downcomer area and the inner part of the vessel, the effect of which during the initial steam dump period is estimated and applied to adjust this model.