CORROSION BEHAVIOR OVERVIEW AND ANALYSIS OF CLAM STEEL VS. WELDMENTS IN LIQUID LITHIUM LEAD AT 753K
Аннотация
Liquid lithium lead material is one of the most promising concepts for the latest fusion reactor blanket design which has been widely investigated. It uses liquid lithium lead as breeding material, lithium for neutron breeding and lead for producing tritium. China, the European Union, the United States and other members of ITER (International Thermonuclear Experimental Reactor) all pay significant attention to the research and development of the liquid lithium lead. The main functions of the lithium lead alloy include energy conversion, tritium breed and radiation shield, it is crucial component in order to make fusion energy to achieve the ultimate applications. However, the concern about liquid metal blanket is its compatibility with candidate structural materials.
Об авторах
Hongyan Cao
School of Material Science and Engineering, Jiangsu University;
School of Mechanical and Electrical Engineering, Wenzhou University
Россия
Россия
Xizhang Chen
School of Mechanical and Electrical Engineering, Wenzhou University
Sergey Konovalov
Department of Metals Technology and Aviation Materials, Samara National Research University
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Рецензия
Для цитирования:
Cao H., Chen X., Konovalov S. CORROSION BEHAVIOR OVERVIEW AND ANALYSIS OF CLAM STEEL VS. WELDMENTS IN LIQUID LITHIUM LEAD AT 753K. Вестник Сибирского государственного индустриального университета. 2017;(1):16-25.
For citation:
Cao H., Chen X., Konovalov S. CORROSION BEHAVIOR OVERVIEW AND ANALYSIS OF CLAM STEEL VS. WELDMENTS IN LIQUID LITHIUM LEAD AT 753K. Bulletin of the Siberian State Industrial University. 2017;(1):16-25. (In Russ.)
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