STRUCTURAL MATERIALS CANDIDATE FOR SUPERCRITICAL WATER-COOLED REACTOR

被引:0
|
作者
Galan, Florentina [1 ]
Budu Stanila, Andrei Razvan [1 ]
机构
[1] Univ Politehn Bucuresti, Dept Power Prod & Usage, Bucharest, Romania
关键词
Supercritical Water-Cooled Reactor (SCWR); structural materials; oxidation; corrosion; CORROSION BEHAVIOR; STAINLESS-STEEL; ALLOYS; OXIDATION;
D O I
暂无
中图分类号
TM [电工技术]; TN [电子技术、通信技术];
学科分类号
0808 ; 0809 ;
摘要
The possibility of making a Supercritical Water-Cooled Reactor (SCWR) will be decided based on the selection of materials that will be able to withstand combined stresses (thermal, hydrostatic, and radiative) that arise from the operating conditions during the life of a reactor. Because supercritical water is a very aggressive corrosive environment, corrosion becomes a difficult problem for materials used in SCWR. This paper summarizes the results of corrosion tests performed so far on promising structural materials for Generation IV water-cooled supercritical reactors. Austenitic stainless steels with Cr and nickel high are promising materials for reactor cladding, as they generally have satisfactory corrosion resistance in supercritical water at high temperatures.
引用
收藏
页码:277 / 286
页数:10
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