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Air-steam leakage through cracks in concrete walls


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Titre de la revue : Nuclear Engineering and Design Volume : 237 N° : SPEC. ISS. 15-17 Pagination : 1786-1794 Date de publication : 01/09/2007

Type de document > *Article de revue

Mots clés > centrales nucléaires REP, fuite

Unité de recherche > IRSN/DSR/SAMS/BAGCS

Auteurs > COULON N., NAHAS Georges, SIMON Hélène

Date de publication > 01/09/2007

Résumé

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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