包层(金属加工)
材料科学
碳化硅
锆
轻水反应堆
冶金
碳化物
锆合金
铝
核工程
工程类
作者
Mamoun I. A. Sagiroun,Xinrong Cao,Anuor A T Ayoub
出处
期刊:IOP conference series
[IOP Publishing]
日期:2020-02-01
卷期号:758 (1): 012085-012085
被引量:3
标识
DOI:10.1088/1757-899x/758/1/012085
摘要
Abstract Iron-chromium-aluminum (FeCrAl) alloys and Silicon-carbide (SiC) are considered the best choice proposed as alternative cladding materials to replace Zirconium (Zr) alloys to improve the accidents tolerance in light water reactor (LWR) cladding which have much highly oxidation resistance in high-temperature steam than Zr alloys, which lead to maintaining high performance under normal operations and enhancing safety margins during severe accidents. In this work great results were showed in the thermo-physical properties for the candidate materials compared with zirconium.
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