包层(金属加工)
应力腐蚀开裂
毯子
核能
腐蚀
核工程
核燃料
材料科学
冶金
工程类
复合材料
核物理学
物理
作者
Yukinori Yamamoto,Mary A. Snead,Kevin G. Field,Kurt A. Terrani
出处
期刊:U.S. Department of Energy Office of Scientific and Technical Information - OSTI OAI
日期:2017-08-01
被引量:37
摘要
FeCrAl alloys are a class of alloys that have seen increased interest for nuclear power applications including as accident tolerant fuel cladding, structural components for fast fission reactors, and as first wall and blanket structures for fusion reactors. FeCrAl alloys are under consideration for these applications due to their inherent corrosion resistance, stress corrosion cracking resistance, radiation-induced swelling resistance, and high temperature oxidation resistance. A substantial amount of research effort has been completed to design, develop, and begin commercial scaling of FeCrAl alloys for nuclear power applications over the past half a century. These efforts have led to the development of an extensive database on material properties and process knowledge for FeCrAl alloys but not within a consolidated format. The following report is the first edition of a materials handbook to consolidate the state-of-the-art on FeCrAl alloys for nuclear power applications. This centralized database focuses solely on wrought FeCrAl alloys, oxide dispersion strengthened alloys, although discussed in brief, are not covered. Where appropriate, recommendations for applications of the data is provided and current knowledge gaps are identified.
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