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Thermal-hydraulic analysis of single and multiple steam generator tube ruptures in a typical 3-loop PWR

Koszela Z., Sokołowski Ł.

Journal of Power Technologies

2015

Vol. 95, nr 3

175--182

The response of the full-scale three-loop Pressurized Water Reactor (PWR) RELAP5 computational model on Steam Generator Break Rupture (SGBR) was investigated in this paper. This model was analyzed in terms of its applicability and performance regarding the research task conducted by Warsaw University of Technology and the National Center for Research and Development inWarsaw, Poland. In the paper break sizes corresponding to one, three and six ruptured tubes (which conform to a Loss-of-Coolant event break size area of 0.02%, 0.054 and 0.11%) were studied at three different locations (at the top of the hot-leg side tubesheet, U-bend and at the top of the cold-leg side tubesheet). The reactor at issue was a three-loop PWR of Westinghouse design with thermal output of 2775 MWt.

RELAP5 Capability to Predict Pressure Wave Propagation Phenomena in Single- and Two-Phase Flow Conditions

Sokolowski Ł., Koszela Z.

Journal of Power Technologies

2012

Vol. 92, nr 3

150--165

Correct evaluation of the hydrodynamic loads induced by large and rapid pressure waves propagating with the speed of sound along the reactor piping systems and Reactor Pressure Vessel (RPV) is an important and difficult issue of nuclear power plant safety. The pressure shock transients and resulting hydrodynamic loads on the pipes and RPV structures are commonly calculated with one-dimensional thermo-hydraulic system codes such as RELAP5, TRACE, DRAKO and ROLAST. In Sweden, the most widely used computer code for this purpose is RELAP5. This code needs, therefore, to be assessed for its capability to predict pressure wave behavior. The conducted assessment involves simulations of single- and two-phase shock-tube problems and two-phase blowdown as well as water hammer experiments. The performed numerical experiments clearly show that RELAP5, with the proper time step and spatial mesh size, is capable of predicting the complex dynamics of single- and two-phase pressure wave phenomena with good to reasonable accuracy.