Critical heat flux and pressure drop tests with vertical upflow of water in a 20-rod bundle of 0. 695-inch diameter rods. [LWBR]

Technical Report · Tue Feb 01 04:00:00 EST 1977

OSTI ID:7225235

Coeling, K J

Steady state and flow coastdown transient critical heat flux (CHF) tests and steady-state pressure drop tests were conducted with a vertical upflow of water in a 20-rod bundle with a 94-inch heated length. Data were obtained at pressures of 1200, 1600, and 2000 psia and at average mass velocities from 0.1 x 10/sup 6/ to 2.0 x 10/sup 6/ lbm/hr-ft/sup 2/. The heat flux distribution was uniform axially but nonuniform transversely. The data presented show that the transient CHF occurred later in the flow coastdown than would be predicted from interpolation of the steady state data.

• Research Organization: Bettis Atomic Power Lab., West Mifflin, PA (USA)
• DOE Contract Number: EY-76-C-11-0014
• OSTI ID: 7225235
• Report Number(s): WAPD-TM-1155
• Country of Publication: United States
• Language: English

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