Theoretical study of steam condensation induced water hammer phenomena in horizontal pipelines

Author:

Barna I. F.12,Pocsai M. A.34,Guba A.5,Imre A. R.67

Affiliation:

1. 1E-mail: barna.imre@wigner.mta.hu, Wigner Research Center of the Hungarian Academy of Sciences, 1121 Budapest, Konkoly Thege út 29–33, Hungary.

2. 2ELI-HU Nonprofit Kft., Dugonics tér 13, 6720 Szeged, Hungary

3. 3E-mail: pocsai.andras@wigner.mta.hu, Wigner Research Center of the Hungarian Academy of Sciences, 1121 Budapest, Konkoly Thege út 29–33, Hungary

4. 4University of Pécs, Faculty of Sciences, Institute of Physics, 7624 Pécs, Ifjúság útja 6, Hungary

5. 5E-mail: guba.attila@energia.mta.hu, Energy Research Center of the Hungarian Academy of Sciences, 1121 Budapest, Konkoly Thege út 29–33, Hungary

6. 6E-mail: imre.attila@energia.mta.hu, Energy Research Center of the Hungarian Academy of Sciences, 1121 Budapest, Konkoly Thege út 29–33, Hungary

7. 7Budapest University of Technology and Economics, Faculty of Mechanical Engineering, Department of Energy Engineering, Muegyetem rkp. 3, D208, H-1111 Budapest, Hungary

Abstract

AbstractSteam condensation induced water hammer (CIWH) phenomena are investigated and new theoretical results are presented. We use the WAHA3 model based on two-phase flow six first-order partial differential equations that present one dimensional, surface averaged mass, momentum and energy balances. A second order accurate high-resolution shock-capturing numerical scheme was applied with different kind of limiters in the numerical calculations. The applied two-fluid model shows some similarities to RELAP5 which is widely used in the nuclear industry to simulate nuclear power plant accidents. This model was validated with different CIWH experiments which were performed in the PMK-2 facility, which is a full-pressure thermohydraulic model of the nuclear power plant of VVER-440/312 type in the Energy Research Center of the Hungarian Academy of Sciences and in the Rosa facility of the Japan Atomic Energy Agency. In our present study we show the first part of a planned large database which will give us the upper and lower flooding mass flow rates for various pipe geometries where CIWH can happen. Such a reliable database would be a great help for future reactor constructions and scheming.

Publisher

Walter de Gruyter GmbH

Subject

Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics,Radiation

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