Results on modeling of primary water stress corrosion cracking at control rod drive mechanism nozzles of pressurized water reactors
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2007
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INTERNATIONAL CONFERENCE ON STRUCTURAL MECHANICS IN REACTOR TECHNOLOGY, 19th
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Resumo
One of the main failure mechanisms that cause risks to pressurized water reactors (PWR) is the primary water
stress corrosion cracking (PWSCC) occurring in alloys like the alloy 600 (75Ni-15Cr-9Fe). It can occur, besides another
places, at the control rod drive mechanism (CRDM) nozzles. It is caused by the joint effect of tensile stress, temperature,
susceptible metallurgical microstructure and environmental conditions of the primary water. These cracks can cause
problems that reduce nuclear safety by blocking the displacement of the control rods and may cause leakage of primary
water that requires repair or replacement of the reactor pressure vessel head. In this work it is performed a study of the
existing models and proposed a new approach to assess the primary water stress corrosion cracking in nickel-based
Alloy 600 CRDM nozzles . The proposed model is obtained from the superposition of electrochemical and fracture
mechanics models, and validated using experimental and literature data. The experimental data were obtained from
CDTN-Brazilian Nuclear Technology Development Center, in a SSRT equipment, according with Schvartzman et
al.(2005).
Staehle (1992) has built a diagram that indicates a thermodynamic condition for the occurrence of some PWSCC
submodes in Alloy 600: it was used potential x pH diagrams (Pourbaix diagrams), for Nickel in high temperature primary
water (3000
C till 3500
C). The PWSCC submodes were located over it, using experimental data. Also, a third parameter
called ìstress corrosion strength fractionî was added. However, it is possible to superimpose to this diagram, other
parameters expressing PWSCC initiation or growth kinetics from other models.
It is important to mention that the main contribution of this work is from a specific experimental condition of
potencial versus pH, it was superposed, an empiric-comparative, according with Staehle (1992), a semi-empiricalprobabilistic according with Gorman et al. (1994), an initiation time according with Garud (1997), and a strain rate
damage according with Boursier et al.(1995)-models, to quantify respectively the PWSCC susceptibility, the failure time,
and in the two lasts, the initiation time of stress corrosion cracking. The results were compared with the literature and it
showed to be coherent. From this work was obtained a modeling methodology from experimental data.
The SSRT tests had been realized at a condition of potential =ñ621 mVSHE and pH= 7.3. The PWSCC strength
fraction evaluated was 0.95: this initiates an empirical-comparative model.
The initiation time model obtained was according Eq. (1) with ti in days, T in K, and σ in MPa. The model was
planned for constant load, but some assumptions were done to obtain (1) from slow strain rate tests.
Como referenciar
ALY, OMAR F.; PAES de ANDRADE, ARNALDO H.; MATTAR NETO, MIGUEL; SCHVARTZMAN, MONICA. Results on modeling of primary water stress corrosion cracking at control rod drive mechanism nozzles of pressurized water reactors. In: INTERNATIONAL CONFERENCE ON STRUCTURAL MECHANICS IN REACTOR TECHNOLOGY, 19th, Aug. 12-17, 2007, Toronto, Canada. Proceedings... Disponível em: http://repositorio.ipen.br/handle/123456789/18443. 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.