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November 9–12, 2025
Washington, DC|Washington Hilton
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Leading the charge: INL’s role in advancing HALEU production
Idaho National Laboratory is playing a key role in helping the U.S. Department of Energy meet near-term needs by recovering HALEU from federal inventories, providing critical support to help lay the foundation for a future commercial HALEU supply chain. INL also supports coordination of broader DOE efforts, from material recovery at the Savannah River Site in South Carolina to commercial enrichment initiatives.
Koichi Hata, Masahiro Shiotsu, Nobuaki Noda
Nuclear Science and Engineering | Volume 154 | Number 1 | September 2006 | Pages 94-109
Technical Note | doi.org/10.13182/NSE06-A2620
Articles are hosted by Taylor and Francis Online.
The critical heat flux (CHF) of subcooled water flow boiling for a high length/diameter (L/d) region is systematically measured for the flow velocities (u = 6.93 to 13.32 m/s), the outlet subcoolings (Tsub,out = 12.5 to 113 K), the inlet subcoolings (Tsub,in = 45 to 148.7 K), the outlet pressure (Pout = 773.50 to 861.12 kPa), and the inlet pressure (Pin = 796.16 to 920.07 kPa). Type 304 stainless steel tubes of inner diameter (d = 2 mm) and heated lengths (L = 21.5, 79.45, and 149.7 mm) with L/d = 10.75, 39.73, and 74.85 are used. The CHF correlation against outlet subcooling including the effect of L/d already presented by the authors describes the CHF obtained in this work within a 15% difference. However, the correlation against inlet subcooling also presented by the authors in the same papers needs a small modification to describe the CHF obtained in this work for a high L/d range. The modified correlation describes not only the experimental data for L/d up to 75 on the 2-mm tube but also the CHF for the same range of L/d on larger diameter tubes predicted by the correlation against outlet subcooling within a 15% difference.
