Small break critical discharge: The roles of vapor and liquid entrainment in a stratified two-phase region upstream of the break
The main objective of this research program was to perform an experimental investigation on the phenomena of two-phase critical flow through small break from a horizontal pipe which contained a stratified two phase flow. Stagnation conditions investigated were saturated steam-water, and air-cold water at pressures ranging from 0.37 MPa to 1.07 MPa. The small breaks employed were cylindrical tubes of diameters 3.96 mm, 6.32 mm, and 10.1 mm with sharp-edged entrance. For breaks resulting from a small hole in a primary coolant pipe or in a small pipe, a sharp-edged orifice or a sharp-edged tube can be the approximation.
- Research Organization:
- Lawrence Berkeley Lab., CA (USA); Nuclear Regulatory Commission, Washington, DC (USA). Div. of Reactor Systems Safety
- DOE Contract Number:
- AC03-76SF00098
- OSTI ID:
- 7010091
- Report Number(s):
- NUREG/CR-4761; LBL-22024; ON: TI87003860
- Country of Publication:
- United States
- Language:
- English
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