ALY, O.F.ANDRADE, A.H.P.MATTAR NETO, M.SZAJNBOK, M.TOTH, H.J.SHIPILOV, S.A.JONES, R.H.OLIVE, J.M.REBAK, R.B.2014-12-172014-12-172014-12-172014-12-172007ALY, O.F.; ANDRADE, A.H.P.; MATTAR NETO, M.; SZAJNBOK, M.; TOTH, H.J. Modeling of primary water stress corrosion cracking (PWSCC) at control rod drive mechanism (CRDM) mozzles of pressurized water reactors (PWR). In: SHIPILOV, S.A. (ed.); JONES, R.H. (ed.); OLIVE, J.M. (ed.); REBAK, R.B. (ed.). <b>Environmenta-induced cracking of materials</b>. p. 143-151. DOI: <a href="https://dx.doi.org/10.1016/b978-008044635-6.50053-4">10.1016/b978-008044635-6.50053-4</a>. Disponível em: http://repositorio.ipen.br/handle/123456789/23002.http://repositorio.ipen.br/handle/123456789/23002One of the main causes of failure in pressurized water reactors (PWR) is the stress corrosion cracking (SCC) at control rods drive mechanism (CRDM) nozzles, produced by tensile stress, temperature, susceptible metallurgical microstructure and environmental conditions of the primary water. Such cracks can cause accidents that reduce nuclear safety by blocking the rods displacement at CRDM and/or leakage of primary water. This paper will present a preliminary development of a model to predict such damage, including initiation and propagation of primary water SCC (PWSCC). The model assumes the Pourbaix potential-pH diagram for Alloy 600 on the typical PWR environment, primary water at high temperature. Over this diagram, the region where the SCC submodes can occur is plotted. Submodes are determined by regions of potential where various modes of surface material-environment interactions can occur, such as stress corrosion, pitting, generalized corrosion or passivation. Over these regions an empiricalprobabilistic is linked to a strain rate damage model that can evaluate the time to failure and the damage parameter, as a function of total stress at the material surface, its temperature and other factors depending on environment-material combination and thermomechanical treatment of this alloy.143-151openAccesspwr type reactorsheat resisting alloyssimulationstress corrosioncrackscontrol elementsnozzlesCapítulo de livro10.1016/b978-008044635-6.50053-4https://orcid.org/0000-0002-2295-1021