DOI: 10.4995/thesis/10251/3839
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Experimental characterization of aerosol retention in the break stage of a dry steam generator in SGTR sequences.

Abstract: Severe accident Steam Generator Tube Rupture (SGTR) sequences are identified as major contributors to risk of Pressurized Water Reactors (PWR). Their relevance lies in the potential radioactive release, in form of aerosol, from reactor coolant system to the environment. However, radioactive particles could be partially retained in the secondary side of the steam generator, even in the absence of water. Lack of knowledge on the source term attenuation capability of the steam generator has avoided its considerat… Show more

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