Effect of steam quality on two-phase flow in a natural circulation loop

Jia Hai-Jun，

Wu Shao-Rong，

Wang Ning，

Yao Si-Min

Nuclear Science and Techniques

Vol.7, No.2

pp.81-84

Published in print 01 May 1996

36900

Test pressures are 1.0〜4.0 MPa, heating powers 27〜190 kW, inlet subcoolings 5〜80℃, water used as coolant, and steam quality at the outlet of test section is less than 0.05. These test conditions cover the parameters for a typical 200 MW heating reactor. The experimental results show that the steam quality is the dominant factor in a natural circulation system with low pressure and low steam quality about the effect of system pressure, heating power and inlet subcooling on the flow rate, relative oscilatory amplitude and oscilatory region of flow rate.

Heating reactorTwo-phase flowInstabilityNatural circulation

References

Tong L S. Nuclear Engineering and Design, 1973; 25: 165-192

Wu S R, Wang D Z, Yao M S et al. Proceedings of the first world conference on experimental heat transfer, fluid mechanics, and thermodynamics. September 4-9, 1988, Dubrovnik, Yugoslavia, New York: Elsevier Publishing Co, 1988: 1120〜1127

Savalskii V P, Kobzar L L, Leppik P A et al.

Stability of the coolant circulation in a model of the AST-500 Reactor

. ATOMHAЯ 3HEP-ΓИЯ; 1983, 55(4): 205〜208

Baidu Scholar

Google Scholar

Wang D Z, Lin J G, Ma C W et al. Nuclear Power Engineering (in Chinese), 1993; 14(4): 289-295

Jia H J, Wu S R, Li H X.

INET Report

, Tsinghua University (in Chinese), 1993

Baidu Scholar

Google Scholar