Two boil-off patterns in rod bundles under high-pressure conditions
It is believed that the nuclear core or steam generator tube bundle becomes partially uncovered due to transient boil-off during a small-break loss-of-coolant accident. In the boil-off, the water inventory in the nuclear core or the steam generator boiling section decreases due to the effluent steam or water. Existing studies have focused on the boil-off experiments in low bundle powers at system pressures from 0.7 to 7.5 MPa. The boil-off experiments in a wide range of bundle powers at system pressures from 3.1 to 11.9 MPa were conducted by using the Two-Phase Flow Test Facility (TPTF). The paper presents a schematic of boil-off patterns in the high or low bundle power considered in the present study. The high and low power boil-off patterns are observed in the TPTF high-pressure boil-off experiments. The difference between the two patterns is considered to be due to the slug-to-annular-flow transition as explained with the present transition model.
- Research Organization:
- Japan Atomic Energy Research Institute, Nakagun
- OSTI ID:
- 5859545
- Report Number(s):
- CONF-851115-; TRN: 86-017887
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 50; Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 10 Nov 1985
- Country of Publication:
- United States
- Language:
- English
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