Preliminary steps toward assessing aerosol retention in the break stage of a dry steam generator during severe accident SGTR sequences

Severe accidents SGTR sequences are identified as major contributors to risk of PWRs. Their relevance lies in the potential radioactive release from reactor coolant system to the environment. Lack of knowledge on the source term attenuation capability of the steam generator has avoided its considera...

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Veröffentlicht in:Nuclear engineering and design 2008-06, Vol.238 (6), p.1392-1399
Hauptverfasser: Herranz, L.E., Prá, C. López del, Velasco, F.J. Sánchez
Format: Artikel
Sprache:eng
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Zusammenfassung:Severe accidents SGTR sequences are identified as major contributors to risk of PWRs. Their relevance lies in the potential radioactive release from reactor coolant system to the environment. Lack of knowledge on the source term attenuation capability of the steam generator has avoided its consideration in probabilistic safety studies and severe accident management guidelines. This paper describes a research program presently under way on the aerosol retention on the tubes surrounding the breach within the secondary side of the steam generator in the absence of water. Its development has been internationally framed within the EU-SGTR and the ARTIST program. Experimental activities are focused on setting up a reliable database in which the influence of gas mass flow rate, breach configuration and particle nature in the aerosol retention are properly considered. Theoretical activities are aimed at developing a predictive tool (ARISG) capable of assessing source term attenuation in the scenario with reasonable accuracy. Given the major importance of jet aerodynamics, 3D CFD analyses are being conducted to assist both test interpretation and model development.
ISSN:0029-5493
1872-759X
DOI:10.1016/j.nucengdes.2007.10.007