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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.
Taku Nagatake, Yasuo Koizumi, Mitsuhiko Shibata, Hiroyuki Yoshida, Yoshiyuki Nemoto, Yoshiyuki Kaji (JAEA)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 414-420
In the Fukushima Daiichi NPP accident, loss of cooling capabilities for spent fuel pool (SFP) occurred. As a result, a water level of the SFP decreased and it was concerned that the spent fuels were damaged. In one of the safety measures for the SFP, a portable spray system is considered as a device to cool the spent fuels.
In this research, the numerical simulation method for evaluating the capability of spray cooling has been developed. To develop this method, we mainly focus on the thermal-hydraulic behavior of two-phase flow generated by the spray cooling systems at the top and inside of the fuel assembly. And an experiment for validating the numerical simulation method also has been performed. In the experiment, by using the experimental apparatus with 5x5 bundle and in order to evaluate the counter current flow limiting (CCFL), visualization of two-phase flow behavior at the upper tie plate is performed and the liquid volume entering into the simulated fuel assembly is measured. In this paper, visualization results of CCFL and CCFL condition of the simulated upper tie plate, and visualization results of developed simulation code are reported.
