Published September 5, 1997 | Version v1
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Effects of oxidation on high-temperature mechanical properties of alloy 600: application to cracking in primary water of nuclear pressurized water reactors

Description

Since the early 1970's certain component parts of the primary loops of nuclear pressurised water reactors, such as steam generator tubing and pressure vessel head penetrations, have been affected by intergranular stress corrosion cracking. This form of cracking, which occurs after several thousand hours, initiates on the component side exposed to primary water. The purpose of this study is to gain a better understanding of the cracking mechanism. The focus is on the interactions between the local mechanical loading conditions and the effects of an oxidising environment. Fatigue and creep fatigue crack propagation tests were carried out using CT specimens. The local mechanical loading conditions were determined by finite element calculations. The oxidation behaviour was studied by transmission electron microscopy. Creep tests were conducted on thin sheet samples to investigate the effects of environment on the creep properties. Intergranular crack propagation, as determined at 550°C in air and in vacuum, has been related to a creep damage mechanism. Dislocation creep deformation mechanisms, which appear to induce intergranular damage in this material at high temperature, are enhanced when the growing oxide scale is nickel- or iron-rich, compared to the results obtained in high vacuum with the protective chromium oxide scale. Thus, intergranular fracture, which occurs in all environmental conditions under creep fatigue cycles, occurs even under fatigue cycles when creep is enhanced. Fatigue crack propagation tests at 400°C gave essentially the same results as those obtained at 550°C. Crack propagation tests in deaerated water, either in low pressure vapour at 400°C or in primary water at 320°C, lead to the same cracking results. The fracture surfaces were identical to those observed after conventional stress corrosion cracking tests. For these environmental conditions, the enhanced creep model was also proposed to account for the experimental results. (author)

Availability note (English)

Also available from Ecole Nationale Superieure des Mines- Bibliotheque, 60 boulevard Saint Michel, 75272 - Paris Cedex 06 (France)

Abstract (French)

La fissuration intergranulaire par corrosion sous contrainte affecte depuis plusieurs decennies certaines pieces en Alliage 600 (NC15Fe) des reacteurs nucleaires a eau sous pression, telles que les tubes de generateur de vapeur et les manchettes d'adaptateur pour couvercle de cuve, exposees pendant plusieurs dizaines de milliers d'heures au milieu primaire (eau pure desaeree, additionnee d'hydrogene, de bore et de lithium entre 290 et 325°C). L'objectif de I'etude est une meilleure comprehension des mecanismes responsables de la fissuration, en particulier des interactions entre les sollicitations mecaniques locales et les effets d'environnement lies.a la presence d'un milieu oxydant. Des essais de propagation de fissure sur eprouvettes CT ont ete realises en fatigue continue et en fatigue-fluage. L'analyse des resultats a porte sur les sollicitations mecaniques locales (calcul par elements finis), les modes d'oxydation (expertises par microscopie electronique en transmission) et les interactions entre l'environnement et le comportement mecanique du materiau (essais sur produit mince). La propagation de fissure intergranulaire a 550°C sous differentes pressions partielles d'oxygene a ete reliee a un endommagement de fluage. La formation d'oxydes riches en nickel et/ou en fer accelere le fluage dislocation a proximite de la surface. Elle etend alors le domaine de rupture intergranulaire vers les vitesses de deformation locales plus elevees imposees en fatigue continue. Des resultats analogues ont ete obtenus a 400°C. Les essais en presence d'eau desaeree (vapeur a 400°C, milieu primaire a 320°C) ont egalement conduit a une propagation de fissure intergranulaire et a la formation d'oxydes riches en nickel. Les facies de rupture sont identiques a ceux obtenus en corrosion sous contrainte. Une activation locale du fluage dislocation par les reactions d'oxydation est egalement envisagee pour rendre compte des resultats experimentaux. (auteur)

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Additional details

Additional titles

Original title (French)
Interactions mecanique-oxydation a haute temperature dans l'alliage 600: application a la fissuration dans le milieu primaire des reacteurs nucleaires a eau sous pression

Publishing Information

Imprint Pagination
337 p.
Report number
FRNC-TH--7518

Optional Information

Notes
234 refs.; Available from the INIS Liaison Officer for France, see the INIS website for current contact and E-mail addresses; This record replaces 39090552