RESEARCH PAPER
Modeling of emergency condenser system response to loss of coolant accident in a BWR III+ generation
More details
Hide details
1
Institute of Heat Engineering, The Faculty of Power and Aeronautical Engineering Warsaw University of Technology ul. Nowowiejska 21/25, 00-665 Warsaw, Poland
2
Thermal Hydraulics and Components Testing, Framatome GmbH Paul-Gossen-Straße 100, 91052 Erlangen, Germany
Publication date: 2019-09-30
Eksploatacja i Niezawodność – Maintenance and Reliability 2019;21(3):468-475
KEYWORDS
ABSTRACT
Emergency Condenser (EC) is a heat exchanger composed of a large number of slightly inclined U-tubes arranged horizontally.
The inlet header of the condenser is connected with the top part of the Reactor Pressure Vessel (RPV), which is occupied by steam
during critical operation. The lower header in turn is linked with the RPV below the liquid water level during normal operation of
the reactor. The tube bundle is filled with cold water and it is located in a vessel filled with water of the same temperature. Thus,
the EC and RPV form together a system of communicating vessels. In case of an emergency and a decrease of the water level in
the RPV, the water flows gravitationally from U-tubes to the RPV. At the same time the steam from the RPV enters to the EC and
condenses due to its contact with cold walls of the EC. The condensate flows then back to the RPV due to the tubes inclination.
Hence, the system removes heat from the RPV and serves as a high- and low-pressure injection system at the same time. In this
paper a model of the EC system is presented. The model was developed with Modelica modeling language and OpenModelica
environment which had not been used in this scope before. The model was verified against experimental data obtained during
tests performed at INKA (Integral Test Facility Karlstein) ̶ a test facility dedicated for investigation of the passive safety systems
performance of KERENA ̶ generation III+ BWR developed by Framatome.
REFERENCES (13)
1.
Areva. UK-EPR, Fundamental Safety Overview, Volume 2: Design and Safety, Chapter R: Probabilistic Safety Assessment 2007.
3.
Bryk R, Schmidt H, Mull T, Ganzmann I, Herbst O. Modeling of the water level swell during depressurization of the reactor pressure vessel of the boiling water reactor in accidental conditions. Eksploatacja i Niezawodnosc – Maintenance and Reliability 2019; 21(1): 28 – 36,
https://doi.org/10.17531/ein.2....
4.
Bryk R, Schmidt H, Mull T, Wagner T, Ganzmann I, Herbst O. Modeling of KERENA Emergency Condenser. Archives of Thermodynamics 2017; 38(4): 29 – 51,
https://doi.org/10.1515/aoter-....
5.
Drescher R, Wagner T, Leyer S. Passive BWR integral LOCA testing at the Karlstein test facility INKA. VGB PowerTech 2014; 5: 33 – 37.
6.
Flage R, Aven T. Expressing and communicating uncertainty in relation to quantitative risk analysis. Reliability and Risk Analysis: Theory and Applications 2009; 2: 9 – 18.
8.
Kind M, Schröder. Subcooled Boiling. VDI Heat Atlas: Chapter H3.3 2010; 804 – 812.
10.
Schaffrath A, Hicken E F, Jaegers H, Prasser H-M. Operation conditions of the emergency condenser of the SWR1000. Nuclear Engineering and Design 1999; 188: 303 – 318,
https://doi.org/10.1016/S0029-....
11.
Shah M M. A general correlation for heat transfer during film condensation inside pipes. International Journal of Heat and Mass Transfer 1979; 22(4): 547 – 556,
https://doi.org/10.1016/0017-9....
12.
Stosic Z V, Brettshuh W, Stoll U. Boiling water reactor with innovative safety concept: the generation III+ SWR-1000. Nuclear Engineering and Design 2008; 238: 1863 – 1901,
https://doi.org/10.1016/j.nuce....
13.
Tandon T N, Varma H K, Grupta C P. A new flow regimes map for condensation inside horizontal tubes. Journal of Heat Transfer 1982; 104(4): 763 – 768,
https://doi.org/10.1115/1.3245....
CITATIONS (1):