Investigation of VVER-1200 reactor pressure vessel's material

被引：0
|
作者：
Kovacs, Dorina [1 ]
Kemeny, David [2 ]
机构：
[1] Budapest Univ Technol & Econ, Fac Mech Engn, Dept Mat Sci & Engn, Muegyet Rakpart 3, H-1111 Budapest, Hungary
[2] Paks II Zrt, Gagarin Utca 1, Paks, Hungary
来源：
12TH HUNGARIAN CONFERENCE ON MATERIALS SCIENCE (HMSC12) | 2020年 / 903卷
关键词：
WATER REACTOR;
D O I：
10.1088/1757-899X/903/1/012051
中图分类号：
O646 [电化学、电解、磁化学];
学科分类号：
081704 ;
摘要：
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 degrees C to 200 degrees 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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页数：5
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