Development of UO2/PuO2 dispersed in uranium matrix CERMET fuel system for fast reactors

Autor:	P.V. Hegde, S. Pal, V.P. Sinha, G.J. Prasad, G.P. Mishra
Rok vydání:	2012
Předmět:	Nuclear and High Energy Physics Liquid metal Materials science Metallurgy Pellets chemistry.chemical_element Cermet Uranium Carbide Breeder (animal) Nuclear Energy and Engineering chemistry visual_art Powder metallurgy visual_art.visual_art_medium General Materials Science Ceramic Nuclear chemistry
Zdroj:	Journal of Nuclear Materials. 427:12-17
ISSN:	0022-3115
DOI:	10.1016/j.jnucmat.2012.04.008
Popis:	CERMET fuel with either PuO 2 or enriched UO 2 dispersed in uranium metal matrix has a strong potential of becoming a fuel for the liquid metal cooled fast breeder reactors (LMR’s). In fact it may act as a bridge between the advantages and disadvantages associated with the two extremes of fuel systems (i.e. ceramic fuel and metallic fuel) for fast reactors. At Bhabha Atomic Research Centre (BARC), R & D efforts are on to develop this CERMET fuel by powder metallurgy route. This paper describes the development of flow sheet for preparation of UO 2 dispersed in uranium metal matrix pellets for three different compositions i.e. U–20 wt%UO 2 , U–25 wt%UO 2 and U–30 wt%UO 2 . It was found that the sintered pellets were having excellent integrity and their linear mass was higher than that of carbide fuel pellets used in Fast Breeder Test Reactor programme (FBTR) in India. The pellets were characterized by X-ray diffraction (XRD) technique for phase analysis and lattice parameter determination. The optical microstructures were developed and reported for all the three different U–UO 2 compositions.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::1d808b999f557c09303155c0b6297902 https://doi.org/10.1016/j.jnucmat.2012.04.008 Zobrazit plný text záznamu Full Text from ScienceDirect