Experimental study of two-phase flow oscillation in natural circulation

Citation
Sy. Jiang et al., Experimental study of two-phase flow oscillation in natural circulation, NUCL SCI EN, 135(2), 2000, pp. 177-189
Citations number
15
Categorie Soggetti
Nuclear Emgineering
Journal title
NUCLEAR SCIENCE AND ENGINEERING
ISSN journal
00295639 → ACNP
Volume
135
Issue
2
Year of publication
2000
Pages
177 - 189
Database
ISI
SICI code
0029-5639(200006)135:2<177:ESOTFO>2.0.ZU;2-F
Abstract
The experiment was performed on the test loop HRTL-5, which simulates the g eometry and system design of the 5-MW nuclear heating reactor developed by the Institute of Nuclear Energy Technology, Tsinghua University. The flow b ehavior for a wide range of inlet subcoolings, in which the flow experience varies from single- to two-phase, is described in a natural circulation sy stem at different pressures (p = 0.1, 0.24 and 1.5 MPa). Several kinds of f low instability are investigated, including geysering, flashing related flo w instability, and high-frequency flow oscillation at p = 0.1 and 0.24 MPa, as well as low steam quality density wave oscillation at p = 1.5 MPa. The mechanisms of geysering, which has new features, and flashing-related flow instability, which has never been studied well enough in this field, are pa rticularly interpreted. The experimental results show the following: First, for a low-pressure natural circulation system, the two-phase flow is unsta ble in most inlet subcooling conditions, and the two-phase stable flow can be reached only with very low inlet subcoolings. Second, at high inlet subc oolings, the flow instability is dominated by subcooling boiling in the hea ted section, and at intermediate inlet subcoolings, it is dominated by void flashing in the adiabatic long riser. Third, in the two-phase stable flow region, the conditions for boiling out of the core, namely, single-phase fl ow in the heated section and two-phase flow in the riser due to vapor flash ing, can be realized. The experimental results are of significance for the design and accident analysis of vessel and swimming pool-type natural circu lation nuclear heating reactors.