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Advanced Reactor PSA Methodologies for System Reliability Analysis and Source Term Assessment

27 Jun 2017, 17:30
1h 30m
Poster Area (Yekaterinburg)

Poster Area

Yekaterinburg

POSTER Track 3. Fast Reactor Safety Poster Session 1

Speaker

Dr David Grabaskas (Argonne National Laboratory)

Description

Beginning in 2015, a project was initiated to update and modernize the probabilistic safety assessment (PSA) of the GE-Hitachi PRISM sodium fast reactor. This project is a collaboration between GE-Hitachi and Argonne National Laboratory (Argonne), and funded in part by the U.S. Department of Energy. Specifically, the role of Argonne is to assess the reliability of passive safety systems, complete a mechanistic source term calculation, and provide component reliability estimates. The assessment of passive system reliability focused on the performance of the Reactor Vessel Auxiliary Cooling System (RVACS) and the inherent reactivity feedbacks mechanisms of the metal fuel core. The mechanistic source term assessment attempted to provide a sequence-specific source term evaluation to quantify offsite consequences. Lastly, the reliability assessment focused on components specific to the sodium fast reactor, including electromagnetic pumps, intermediate heat exchangers, the steam generator, and sodium valves and piping.

Country/Int. Organization

USA/Argonne National Laboratory

Primary authors

Dr Acacia Brunett (Argonne National Laboratory) Mr Austin Grelle (Argonne National Laboratory) Dr David Grabaskas (Argonne National Laboratory) Dr Stefano Passerini (Argonne National Laboratory)

Presentation materials