2013
DOI: 10.1016/j.nucengdes.2013.06.013
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Microstructural study of WWER reactor pressure vessel steels

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Cited by 8 publications
(2 citation statements)
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“…These attributes must be studied especially in the case of stainless steels that are used as a basic material for construction of various components of nuclear installations. [1][2][3] It is apparent that in various alloys, chromium has anticorrosion properties because of formation of surface segregation and passivation layer. [4][5][6][7] That is why stainless steels with high amount of chromium are suitable candidates for constructions of nuclear reactor pressure vessels.…”
Section: Introductionmentioning
confidence: 99%
“…These attributes must be studied especially in the case of stainless steels that are used as a basic material for construction of various components of nuclear installations. [1][2][3] It is apparent that in various alloys, chromium has anticorrosion properties because of formation of surface segregation and passivation layer. [4][5][6][7] That is why stainless steels with high amount of chromium are suitable candidates for constructions of nuclear reactor pressure vessels.…”
Section: Introductionmentioning
confidence: 99%
“…), and the original microstructure (phase, grain boundary size). [5][6][7][8] However, due to the microstructure complexity of the irradiated materials and the objective limitation of service environment, it is very hard to study and predict the long-term evolution of microstructures through experimental methods. [9,10] Therefore, the research on simulation methods have been paid more focuses.…”
Section: Introductionmentioning
confidence: 99%