Fabrication of (Pu[sub 0. 55]U[sub 0. 45]C) fuel pellets for the second core of the Fast Breeder Test Reactor in India

Journal Article · Tue Mar 01 00:00:00 EST 1994 · Nuclear Technology; (United States)

OSTI ID:5107341

Ganguly, C; Hegde, P V; Jain, G C ^[1]

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1. Bhabha Atomic Research Center, Bombay (India). Radiometallurgy Div.

Around 200 kg of (Pu[sub 0.55]U[sub 0.45]) C fuel pellets of relatively low density (86[+-]2% theoretical density) would be used as a driver fuel in the second core of the Fast Breeder Test Reactor in India. The current paper summarizes the production experience of the initial 15 kg of these fuel pellets following the vacuum carbothermic synthesis'' of tableted oxide-graphite powder mixture followed by cold-pelletization'' of carbide powder and sintering''. The alterations made in the process equipment, radiation shielding arrangements, and fabrication parameters have been highlighted. The carbothermic synthesis and sintering were carried out in batches of 600 g and 1 kg, respectively. The percentage recovery of sintered pellets in all the batches was > 90%. The resintering tests of pellets showed only marginal change in sintered density, ensuring minimum in-pile densification.

• OSTI ID: 5107341
• Journal Information: Nuclear Technology; (United States), Vol. 105:3; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
MIXED CARBIDE FUELS
FABRICATION
TEST REACTORS
NUCLEAR FUELS
PLUTONIUM CARBIDES
URANIUM CARBIDES
ACTINIDE COMPOUNDS
CARBIDES
CARBON COMPOUNDS
ENERGY SOURCES
FUELS
MATERIALS
PLUTONIUM COMPOUNDS
REACTOR MATERIALS
REACTORS
RESEARCH AND TEST REACTORS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
050700* - Nuclear Fuels- Fuels Production & Properties
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors