[en] Steam generator tube rupture (SGTR) events have a low probability of occurrence, but if they occur, they might lead to the escape of radio nuclides from the primary circuit to the secondary side, and subsequent emissions to the environment bypassing the containment. In western pressurized water reactors (PWR), SGTR is a design basis accident (DBA) and the plants are designed to cope with it. However, a particular safety challenge arises from an SGTR in combination with other failures resulting in a core melt, and radioactive fission product release from the core. The source term into the environment is determined by the release of fission products from the core and their retention in their release path through the steam generator. Based on the need for aerosol retention data during an SGTR, EU-SGTR project was carried out in 2000-2002. It was followed by international collaboration projects ARTIST (Aerosol Trapping In a Steam Generator, 2003-2007) and ARTIST II (2008-2011), coordinated by the Paul Scherrer Institut (PSI). In these projects, aerosol retention in the steam generator was investigated both experimentally and analytically. Integral experiments for aerosol retention in the ARTIST facility, which is a scaled-down model of the FRAMATOME 33/19 type steam generator, showed significant retention of aerosols in the steam generator during SGTR. In this paper, we will briefly summarize some of the main conclusions of the ARTIST projects. The main emphasis of this work is the extension of the research by estimating the offsite consequences (doses) that could be expected from an SGTR, and the reduction in these consequences due to the acquired understanding of the behavior of the fission product transport and retention in the secondary side of a PWR steam generator from the ARTIST projects. MELCOR calculations have been performed for such an accident and the results for releases of a Spontaneous Steam Generator Tube Rupture (S-SGTR) accident are used for the main part of the work. Assessment of consequences is performed using the USNRC code MACCS2. (authors)