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U.S. Department of Energy
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STEAM SEPARATION TECHNOLOGY UNDER THE EURATOM PROGRAM. Quarterly Progress Report, July 1, 1963-September 30, 1963

Technical Report ·
DOI:https://doi.org/10.2172/4701472· OSTI ID:4701472
Calibration of the liquid-level detector for steam-water facility is complete from 600 to 2000 psig. Permissible steam release rates for 24 and 36 inches above the interface are established for the test pressures. The correlalation equation which relates steam void fraction to basic system parameters is further refined to include ail the data from this program as well as from the low-pressure steam-water facility. By addition of another dimensionless term to the equation it is possible to extend the equation to include the radial gradient in the void fraction. Collection of carryunder in the downcomer region of the natural separation reactor mockup is complete. From this data it is possible to establish an equation for the downcomer slip ratio. The development of two types of upcomer separators is discussed: a small separator to fit over a fuel element or a group of elements, and a large separator to get over an entire core. The initial small separator under investigation is a centrifugal axial flow model. Results from this program are encouraging. The large upcomer models tested are of the double-helix type. Results with these separators are not encouraging, but data from the small separator program should provide useful information to aid the large separator design. Analysis of the test results from the 8-in. diameter centrifugal type downcomer separator is complete. The test provides a check on the equations used to scale from one size separator to another. It appears that the equations are conservative, predicting a lower capacity than the test shows. (auth)
Research Organization:
Allis-Chalmers Mfg. Co. Atomic Energy Div., Milwaukee
NSA Number:
NSA-17-040954
OSTI ID:
4701472
Report Number(s):
ACNP-63028; EURAEC-828
Country of Publication:
United States
Language:
English