2007
DOI: 10.1016/j.ijpvp.2007.04.004
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Radiation stability of WWER RPV cladding materials

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Cited by 11 publications
(4 citation statements)
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“…On the other hand, the impact of cladding on the reactor pressure vessel wall integrity has been investigated in a very limited way in spite of the fact that it can potentially be of great significance to RPV integrity. The reason is that plasticity and the elevated fracture toughness of cladding can provide additional strength to the pressure wall and this process can justify an extended reactor lifetime [30]. In addition, in thermal expansion coefficients, significant differences can be found with respect to pressure vessel base metals, which can cause a stress peak [31].…”
Section: Introductionmentioning
confidence: 99%
“…On the other hand, the impact of cladding on the reactor pressure vessel wall integrity has been investigated in a very limited way in spite of the fact that it can potentially be of great significance to RPV integrity. The reason is that plasticity and the elevated fracture toughness of cladding can provide additional strength to the pressure wall and this process can justify an extended reactor lifetime [30]. In addition, in thermal expansion coefficients, significant differences can be found with respect to pressure vessel base metals, which can cause a stress peak [31].…”
Section: Introductionmentioning
confidence: 99%
“…The fracture toughness test results of austenitic cladding usually exhibit a sharp transition curve, in the shape of hyperbolic tangent, similarly to the ferritic steels. This anomaly of the cladding from other austenitic steels is caused by the relatively a high amount of delta ferrite contained in the cladding (3-8%) [1,2]. As can be seen from the graphs in Fig.…”
Section: Resultsmentioning
confidence: 83%
“…In spite of this fact, not much attention has yet been devoted to the fracture properties of the cladding materials [1]. Different regulatory approaches allow the inclusion of the cladding in the RPV integrity assessment, provided that its properties are known during the RPV lifetime [2]. Therefore, obtaining knowledge of fracture mechanisms of the individual cladding layers, as well as obtaining knowledge on the effect of the neutron irradiation of the austenitic cladding, is essential [3].…”
Section: Introductionmentioning
confidence: 99%
“…In pressurized water reactor (PWR) systems, nominally austenitic stainless steels (SS), which contain a certain amount of ferrites, are cladded onto the reactor pressure vessel steel, the low alloy steel (LAS) nozzle portion in the dissimilar weld, and other components as an isolation barrier between the low alloy steel and the primary water environments [1][2][3][4][5][6]. The compositions of austenitic weld metals are typically opted to promote primary solidification as δ-ferrite and a solid-state transformation to austenite to prevent hot cracking during the cladding process [2,7]. The as-cladded microstructure often retains some volume percentages of the body-centered cubic (bcc) ferrite phase at room temperature, leading to a duplex austenitic-ferritic microstructure [8].…”
Section: Introductionmentioning
confidence: 99%