Journal
JOURNAL OF NUCLEAR MATERIALS
Volume 466, Issue -, Pages 21-28Publisher
ELSEVIER
DOI: 10.1016/j.jnucmat.2015.07.010
Keywords
Nuclear grade zirconium; Production; Hafnium removal; Technology overview; Molten salt extraction
Funding
- National Natural Science Foundation of China (NSFC) [51274005, 51174055]
- Chinese Scholarship Council (CSC)
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Zirconium is an ideal material for nuclear reactors due to its low absorption cross-section for thermal neutrons, whereas the typically contained hafnium with strong neutron-absorption is very harmful for zirconium as a fuel cladding material. This paper provides an overview of the processes for nuclear grade zirconium production with emphasis on the methods of Zr-Hf separation. The separation processes are roughly classified into hydro- and pyrometallurgical routes. The known pyrometallurgical Zr-Hf separation methods are discussed based on the following reaction features: redox characteristics, volatility, electrochemical properties and molten salt metal equilibrium. In the present paper, the available Zr-Hf separation technologies are compared. The advantages and disadvantages as well as future directions of research and development for nuclear grade zirconium production are discussed. (C) 2015 Elsevier B.V. All rights reserved.
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