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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.
W. Breitung, K. O. Reil
Nuclear Science and Engineering | Volume 101 | Number 1 | January 1989 | Pages 26-40
Technical Paper | doi.org/10.13182/NSE89-A23592
Articles are hosted by Taylor and Francis Online.
Newly developed in-pile techniques were used to measure the saturation vapor pressure of pure UO2.01, reactor grade UO2.08, and reactor grade (U0.77Pu0.23)O2.09 between 2000 and 3700 kJ/kg. The results for all three fuel types can be described by log Psat (z) = -9.7652 + 8.0934 × 10-3z - 2.0515 × 10-6z2 + 1.9013 × 10-10z3 with z = h-h298 in kilojoules per kilogram and psat in megapascals. The data were converted to the pressure-temperature format and compared to earlier out-of-pile vapor pressure measurements. All out-of-pile measurements that were performed close to a vapor-liquid equilibrium state agree very well with the in-pile results. The following relation is proposed for the p-T saturation line of liquid UO2: log psat (T) = 15.961 - 26974/T - 2.7600 log T, with psat in megapascals and T in degrees kelvin. Because no significant differences were found for all three fuel types investigated, the same saturation vapor pressure is recommended for liquid-metal fast breeder reactor (LMFBR) typical (U,Pu) mixed oxides under LMFBR core disassembly conditions.
