Published January 2018 | Version v1
Book

Sintering study of nanocrystalline (U1-xCex)O2 (x = 0.22 and 0.28) by dilatometry

  • 1. Indira Gandhi Centre for Atomic Research, Kalpakkam (India)

Description

The uranium plutonium mixed oxides (MOX) are used as fuel in sodium cooled fast reactors (SFR). Indian Prototype Fast Breeder Reactor (PFBR), employs mixed oxides of uranium and plutonium with the composition (U1-xPux)O2 (x = 0.22,0.28). These fuels are fabricated through conventional powder metallurgical route. Often it difficult to obtain a product with a good micro-homogeneity when conventional powder metallurgical fabrication routes are employed. Solution based methods not only yield a product with better micro homogeneity, but also results in a highly sinter crystalline solid solution. Owing to the similarities of its chemical properties to that of plutonium, cerium is often considered as a surrogate for the latter. Hence, in the present study sintering behave on Nano crystalline (U1-xCex)O2 (x = 0.22, 0.28) was carried out by dilatometric method

Part of:
Proceedings of the twenty-first DAE-BRNS symposium on thermal analysis

Additional details

Publishing Information

Publisher
Indian Thermal Analysis Society
Imprint Place
Mumbai (India)
Imprint Title
Proceedings of the twenty-first DAE-BRNS symposium on thermal analysis
Imprint Pagination
179 p.
Journal Page Range
p. 118

Conference

Title
21. DAE-BRNS symposium on thermal analysis
Acronym
THERMANS-2018
Dates
18-20 Jan 2018
Place
Goa (India)

Optional Information

Notes
4 refs., 3 figs.