Computational Simulation of Test 1.1 of the PKL-2 Project in the Rocom Facility Using TRACE Code System
DOI:
https://doi.org/10.70567/mc.v42.ocsid8283Keywords:
Nuclear reactors, Thermohydraulic calculation, Main steam line break, TRACEAbstract
TRACE5 is a system code designed to perform simulations of operational transients and accidents in nuclear reactors. It is capable of simulating certain areas of a nuclear power plant using a monolithic 3D discretization tool which allows the representation of geometrically complex regions. In the present work, it was employed to analyze the temperature distribution in the downcomer and the lower plenum of the ROCOM experimental facility, which represents a KONVOI reactor at a 1:5 scale, during test 1.1 of the PKL-2 project. These conditions correspond to the sudden cooling stage in the primary system resulting from a main steam line break accident. As part of the study, it is planned to analyze the sensitivity to different levels of geometric refinement and the capability to reproduce coolant temperature variations. Based on the results obtained with TRACE, it was concluded that they show good agreement with the experimental values.
References
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Página web oficial de ROCOM: https://www.hzdr.de/db/Cms?pOid=11974&pNid=2737
Página official Proyecto PKL de la OECD: www.oecd-nea.org/jcms/pl_25236/primarycoolant-loop-test-facility-pkl-project.
Coscarelli, E., An Integrated Approach to Accidente Analysis in PWR, Universitá di Pisa, 2013
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