Intergranular Embrittlement of Nuclear Reactor Pressure Vessel Steels

Oleg O. Zabusov; Boris A. Gurovich; Evgenia A. Kuleshova; Michail A. Saltykov; Svetlana V. Fedotova; Alexey P. Dementjev

doi:10.4028/www.scientific.net/KEM.592-593.577

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Intergranular Embrittlement of Nuclear Reactor Pressure Vessel Steels

Abstract:

Service life of VVER-type nuclear reactor is limited by decrease in brittle fracture resistance of reactor pressure vessel produced of low-alloy low-carbon steel under effect of irradiation and/or elevated temperatures. In this work fracture surfaces were studied by Auger-electron spectroscopy in order to estimate the contribution of intergranular embrittlement to the degradation of reactor pressure vessel steels under the influence of operating conditions. It was demonstrated that irradiation induced segregation leads to an increase of P content in grain boundaries that promotes intergranular brittle fracture on fracture surfaces. The similar effect but to a lesser degree was shown in the case of long-term temperature exposure. The grain boundary structure was examined and an effect of carbides located on the grain boundaries is supposed due to increased phosphorus segregation on carbide/matrix interface boundaries.

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Periodical:

Key Engineering Materials (Volumes 592-593)

Pages:

577-581

DOI:

https://doi.org/10.4028/www.scientific.net/KEM.592-593.577

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Online since:

November 2013

Authors:

Oleg O. Zabusov*, Boris A. Gurovich, Evgenia A. Kuleshova, Michail A. Saltykov, Svetlana V. Fedotova, Alexey P. Dementjev

Keywords:

Auger-Electron Spectroscopy, Embrittlement, Grain Boundary, Irradiation, Reactor Pressure Vessel, VVER-1000

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References

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