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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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.
K. Y. Suh, R. J. Hammersley
Nuclear Science and Engineering | Volume 109 | Number 1 | September 1991 | Pages 26-38
Technical Paper | doi.org/10.13182/NSE91-A23842
Articles are hosted by Taylor and Francis Online.
Best-estimate calculations of realistic source terms are presented that reduce uncertainties in predicting volatile fission product release from the UO2 fuel over the temperature range from 770 to 2500 K. The proposed method of correlation includes such fuel morphology effects as equiaxed fuel grain growth and fuel/cladding interaction. The method correlates the product of fuel release rate and equiaxed grain size with the inverse fuel temperature to yield a bulk mass transfer correlation. It is found that fewer and slower releases are predicted utilizing the bulk mass transfer correlation than with the steam oxidation model and the U.S. Nuclear Regulatory Commission’s NUREG-0956 correlation. Computational modules are developed to perform the thermal-hydraulic and fission product calculations needed to analyze the severe fuel damage tests. The predictions utilizing the bulk mass transfer correlations overall follow the experimental time-release histories during the heatup, power hold, and cooldown phases of the transients. Good agreements are achieved for the integral releases both in timing and in magnitude. The proposed bulk mass transfer correlations can be applied to both current and advanced light water reactor fuels.