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B. W. LeTourneau, M. E. Gavin, S. J. Green
Nuclear Science and Engineering | Volume 54 | Number 2 | June 1974 | Pages 214-232
Technical Note | doi.org/10.13182/NSE74-A23411
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Critical heat flux and pressure drop tests were run with vertical upflow of water parallel to 20-rod bundles of rods at 1200 to 2000 psia and mass velocities from 0.15 × 106 to 3.0 × 106 lb/(h ft2). The heated rods were 0.75-in. o.d. × 94-in. heated length, spaced by warts in a 5 × 4 array on a 0.765-in. equilateral-triangular pitch in a rhombic shroud box. Tests were run both with all rods uniformly heated and with a linear-transverse heat-flux distribution, with and without protrusions to minimize the effect of large peripheral channels.
