期刊
JOURNAL OF NUCLEAR MATERIALS
卷 436, 期 1-3, 页码 130-138出版社
ELSEVIER SCIENCE BV
DOI: 10.1016/j.jnucmat.2013.01.310
关键词
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资金
- R&D program of the Korea Evaluation Institute of Industrial Technology (KEIT)
- Ministry of Knowledge Economy, Korea [10040084]
- national nuclear long-term research and development program
- Ministry of Science and Technology, Korea
- Korea Evaluation Institute of Industrial Technology (KEIT) [10040084] Funding Source: Korea Institute of Science & Technology Information (KISTI), National Science & Technology Information Service (NTIS)
Zirconium (Zr) has commonly been used as a cladding material of nuclear fuel. Moreover, it is regarded as the only material that can be used for nuclear fuel cladding because it has the lowest neutron capture cross section of any metal element and because it has high corrosion resistance and.size stability. In this study, Hf-free Zr tubes (Zr-1Nb-1Sn-0.1Fe) were used as anode materials and electrorefining was performed in a LiF-KF eutectic 6 wt.% ZrF4 molten fluoride salt system. As a result of electrolysis, Zr scrap metal was recycled into pure Zr with low levels of impurities, and the size and density of the Zr deposit was controlled using applied current density. (c) 2013 Elsevier B.V. All rights reserved.
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