Preliminary study for extension and improvement on modeling of primary water stress corrosion cracking at control rod drive mechanism nozzles of pressurized water reactors
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2009
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INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 9th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 16th; MEETING ON NUCLEAR INDUSTRY, 1st
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This study is for to extend, to improve the existing models, and to propose a local approach to
assess the primary water stress corrosion cracking in nickel-based components. It is includes
a modeling of new data for Alloy 182 and new considerations about initiation and crack
growth according a developing method based on EPRI-MRP-115 (2004), and USNRC
NUREG/CR-6964 (2008). The experimental data is obtained from CDTN-Brazilian Nuclear
Technology Development Center, by tests through slow strain rate test (SSRT) equipments.
The model conception assumed is a built diagram which indicates a thermodynamic condition
for the occurrence of corrosion submodes in essayed materials, through Pourbaix diagrams,
for Nickel Alloys in high temperature primary water. Over them, are superimposed different
models, including a semi-empiric-probabilistic one to quantify the primary water stress
corrosion cracking susceptibility, and a crack growth model. These constructed models shall
be validated with the experimental data.
This development aims to extent some of the models obtained to weld metals like the Alloy
182, and to improve the originals obtained according methodologies exposed in above
referred reports. These methodologies comprise laboratory testing procedures, data
collecting, data screening, modeling procedures, assembling of data from some laboratories
in the world, plotting of results, compared analysis and discussion of these results.
Preliminary results for Alloy 182 will be presented.
Como referenciar
ALY, OMAR F.; MATTAR NETO, MIGUEL; SCHVARTZMAN, MONICA M.M.A.M. Preliminary study for extension and improvement on modeling of primary water stress corrosion cracking at control rod drive mechanism nozzles of pressurized water reactors. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 9th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 16th; MEETING ON NUCLEAR INDUSTRY, 1st, September 27 - October 2, 2009, Rio de Janeiro, RJ. Proceedings... Disponível em: http://repositorio.ipen.br/handle/123456789/16643. Acesso em: 30 Dec 2025.
Esta referência é gerada automaticamente de acordo com as normas do estilo IPEN/SP (ABNT NBR 6023) e recomenda-se uma verificação final e ajustes caso necessário.