A study using RELAP5 on capability and instability of two-phase natural circulation flow under passive external reactor vessel cooling

Author:

Guozhi Zhao,Xinrong Cao,Xingwei Shi

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference22 articles.

1. Dinh, T.N., Tu, J.P., Salmassi, T., Theofanous, T.G., 2003. Limits of Coolability in the AP1000-Related ULPU-2400 Configuration V Facility. CRSS-03006, Center for Risk Studies and Safety, University of California, Santa Barbara.

2. Energy Research, Inc., 2004. Analysis of In-vessel Retention and Ex-vessel Fuel Coolant Interaction for AP1000. ERI/NRC-04-201, USA, pp. 20–55.

3. Classification of two-phase flow instability by density wave oscillation model;Fukuda;Journal of Nuclear Science and Technology,1979

4. Evaluations of two-phase natural circulation flow induced in the reactor vessel annular gap under ERVC conditions;Ha;Nuclear Engineering and Design,2012

5. Analysis of two-phase flow characteristics in a natural circulation loop using the drift-flux model taking flow pattern change and subcooled boiling into consideration;Jeng;Annals of Nuclear Energy,1999

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