BARC/PUB/2014/0761

 
 

Study on Alloying Behaviour of Uranium Zirconium Alloy

 
     
 
Author(s)

Bagchi, A. C.; Prasad, G. J.; Khan, K. B.; Singh, R. P.
(NFG)

Source

Transactions of the Indian Institute of Metals, 2014. Vol. 67 (3): pp. 443-449

ABSTRACT

Uranium–zirconium alloy is the potential candidate material as metallic fuels for nuclear reactor applications. Fabrication of uranium zirconium alloy can be made either by powder metallurgy or by melting method. Both the method has its own advantages and selection of the fabrication route depends on its application as fuel. In this work investigations were carried out on fabrication of uranium– zirconium alloys (i.e. U–40 wt% Zr, U–50 wt% Zr, U–60 wt% Zr and U–70 wt% Zr) using both powder metallurgy and melting method. It is heat treated at different conditions. Apart from other characterization, X-ray diffraction analysis was carried out to evaluate phase content of the alloy and reported here.

 
 
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