《能源前沿（英文）》
>> 2009年
第3卷
第2期
doi:
10.1007/s11708-009-0030-0
RESEARCH ARTICLE
Feasibility analysis of modified AL-6XN steel for structure component application in supercritical water-cooled reactor
Institute of Nuclear Materials, University of Science and Technology Beijing, Beijing 100083, China
发布日期：
2009-06-05
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摘要
Modified AL-6XN austenite steel was patterned after AL-6XN superaustenitic stainless steel by introducing microalloy elements such as zirconium and titanium in order to adapt to recrystallizing thermo-mechanical treatment and further improve crevice corrosion resistance. Modified AL-6XN exhibited comparable tensile strength, and superior plasticity and impact toughness to commercial AL-6XN steel. The effects of aging behavior on corrosion resistance and impact toughness were measured to evaluate the qualification of modified AL-6XN steel as an in-core component and cladding material in a supercritical water-cooled reactor. Attention should be paid to degradation in corrosion resistance and impact toughness after aging for 50 hours when modified AL-6XN steel is considered as one of the candidate materials for in-core components and cladding tubes in supercritical water-cooled reactors.
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