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Air-steam leakage through cracks in concrete walls


Journal title : Nuclear Engineering and Design
Volume : 237
Issue : SPEC. ISS. 15-17
Pagination : 1786-1794
Publication date : 01/09/2007

Document type > *Article de revue

Keywords > leakage, PWR nuclear power plants

Research Unit > IRSN/DSR/SAMS/BAGCS

Authors > COULON N., NAHAS Georges, SIMON Hélène

Publication Date > 01/09/2007

Summary

In the context of a severe accident in a PWR nuclear plant, the evaluation of the leakage through the containment wall remains a key point of the safety analysis. Here we calculate the leakage of an air steam mixture through a traversing crack taking into account condensation. A 40 h test has been performed on a representative concrete slab with measurements of crack openings and flow rates. The CAST3M code enables us to simulate this test by making thermo-mechanical calculations and calculation of the leakage flow rate. Thermo-mechanical calculations provide data needed by the leakage calculations which are not measurable in the experiment. These are the internal crack profiles (variation of the opening with the curvilinear coordinate of the crack inside the concrete slab). Thermo-mechanical calculations are difficult to perform because boundary conditions of the test are complicated. Leakage calculations are performed with various hypotheses for the internal cracks profiles. A coefficient is applied on the friction factor to take into account additional complexity of the crack geometry

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