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In transition: Commercializing fusion power
Commercial fusion power is closer than ever. There are now around 30 U.S. fusion companies, several of which claim to be on track to connect to the grid as early as the 2030s.
Tokamak and laser inertial confinement approaches benefit from decades of research at facilities such as the National Ignition Facility (NIF) at Lawrence Livermore National Laboratory and ITER, with alternative concepts including stellarator, magnetic mirror, and Z-pinch confinement also making notable progress as private and government funding for fusion increases.
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.