Investigation of VVER-1200 reactor pressure vessel’s material | Zendy

Dorina Kovács | Zendy; Dávid Kemény | Zendy

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Investigation of VVER-1200 reactor pressure vessel’s material

Author(s) -

Dorina Kovács,

Dávid Kemény

Publication year - 2020

Publication title -

iop conference series materials science and engineering

Language(s) - English

Resource type - Journals

eISSN - 1757-899X

pISSN - 1757-8981

DOI - 10.1088/1757-899x/903/1/012051

Subject(s) - charpy impact test , vver , reactor pressure vessel , pressure vessel , materials science , metallurgy , alloy , corrosion , pressurized water reactor , irradiation , composite material , nuclear engineering , microstructure , nuclear physics , physics , engineering

At high temperature and pressure, the reactor materials are exposed to various radiation. Irradiation causes significant changes in the crystal structure and their mechanical properties. The mechanical properties of low alloy steels generally do not change so much with temperature. The aim of this research is to prepare the basic measurements to investigate 15Cr2NiMoVA steel, according to MSZ EN ISO 148-1:2017. Charpy impact test was made at different temperatures from -75 °C to 200 °C. Potentiodynamic tests were used to determine the corrosion rate. During the optical microscopy measurement, MnS inclusions were found in the examined material.

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