Published 2009 | Version v1
Book

Fabrication of mixed uranium-plutonium carbide fuel pellets for FBTR from reject pellets and process scraps by dry route

  • 1. Radiometallurgy Division, Bhabha Atomic Research Centre, Mumbai (India)

Description

Mixed uranium-plutonium carbide fuel pellets of compositions 70%PuC-30%UC (Mk I) and 55%PuC-45%UC (Mk II) encapsulated in stainless steel clad tubes are being used as driver fuel for Fast Breeder Test Reactor at Kalpakkam. In B.A.R.C., the manufacture of fuel pins is being carried out for almost twenty five years in several fabrication campaigns to meet the fuel requirements. Production of mixed uranium-plutonium carbide pellets are carried out in batches of one kilogram and the process flow sheet involves vacuum carbothermic reduction of UO2, PuO2 and graphite mixture tablets for synthesis of carbide clinkers followed by milling, cold compaction and sintering. The fabrication is carried out in glove boxes maintained in high purity nitrogen atmosphere with less than 25 ppm of oxygen and moisture impurities, since the carbide powders are pyrophoric in nature and are also susceptible to oxidation and hydrolysis

Part of:
Proceedings of the third international conference on characterization and quality control of nuclear fuels

Additional details

Publishing Information

Publisher
Nuclear Fuel Complex
Imprint Place
Hyderabad (India)
Imprint Title
Proceedings of the third international conference on characterization and quality control of nuclear fuels
Imprint Pagination
186 p.
Journal Page Range
2 p.

Conference

Title
3. international conference on characterization and quality control of nuclear fuels
Acronym
CQCNF-2009
Dates
18-20 Feb 2009
Place
Hyderabad (India)

Optional Information