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http://dx.doi.org/10.1016/j.net.2016.06.001

Key Findings from the Artist Project on Aerosol Retention in a Dry Steam Generator  

Dehbi, Abdelouahab (Nuclear Energy and Safety Research Department, Paul Scherrer Institute)
Suckow, Detlef (Nuclear Energy and Safety Research Department, Paul Scherrer Institute)
Lind, Terttaliisa (Nuclear Energy and Safety Research Department, Paul Scherrer Institute)
Guentay, Salih (Nuclear Energy and Safety Research Department, Paul Scherrer Institute)
Danner, Steffen (Nuclear Energy and Safety Research Department, Paul Scherrer Institute)
Mukin, Roman (Nuclear Energy and Safety Research Department, Paul Scherrer Institute)
Publication Information
Nuclear Engineering and Technology / v.48, no.4, 2016 , pp. 870-880 More about this Journal
Abstract
A steam generator tube rupture (SGTR) event with a stuck-open safety relief valve constitutes one of the most serious accident sequences in pressurized water reactors (PWRs) because it may create an open path for radioactive aerosol release into the environment. The release may be mitigated by the deposition of fission product particles on a steam generator's (SG's) dry tubes and structures or by scrubbing in the secondary coolant. However, the absence of empirical data, the complexity of the geometry, and the controlling processes have, until recently, made any quantification of retention difficult to justify. As a result, past risk assessment studies typically took little or no credit for aerosol retention in SGTR sequences. To provide these missing data, the Paul Scherrer Institute (PSI) initiated the Aerosol Trapping In Steam GeneraTor (ARTIST) Project, which aimed to thoroughly investigate various aspects of aerosol removal in the secondary side of a breached steam generator. Between 2003 and 2011, the PSI has led the ARTIST Project, which involved intense collaboration between nearly 20 international partners. This summary paper presents key findings of experimental and analytical work conducted at the PSI within the ARTIST program.
Keywords
Containment Bypass; Fission Product Retention; Steam Generator Tube Rupture;
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