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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.
Robert L. Kiang
Nuclear Science and Engineering | Volume 89 | Number 3 | March 1985 | Pages 207-216
Technical Paper | doi.org/10.13182/NSE85-A17542
Articles are hosted by Taylor and Francis Online.
Concerns about nuclear power plant safety have stimulated research in thermal hydraulics of reactor cooling systems. Complementary efforts in computer code development and in experiments using scaled models are being made. The applicability of the experimental results to a full-size power plant system depends on the scaling criteria on which the test facility is designed. Several sets of scaling criteria can be found in the literature, not all of them compatible with one another. A critical review and clarification of a number of these scaling criteria are presented. Specifically, the commonly recognized linear scaling, volume scaling, and several sets of single- and two-phase scaling criteria recently derived by M. Ishii are examined in terms of their limitations and interrelationships. It is shown that (a) as far as thermal-hydraulic modeling is concerned, Ishii's time-distorted scaling is the most general one to date, (b) Ishii's scaling offers the model designer a flexibility in the height of the model, and (c) both the linear and volume scaling are special cases of the Ishii scaling, and each has its own practical limitations.