American Nuclear Society
Home

Home / Publications / Journals / Nuclear Technology / Volume 72 / Number 1

Development and Fabrication of 70% PuC—30% UC Fuel for the Fast Breeder Test Reactor in India

Chaitanyamoy Ganguly, Parameshwar Venkappa Hegde, Gyan Chand Jain, Uddharan Basak, Radhey Shyam Mehrotra, Sukomal Majumdar, Pradip Ranjan Roy

Nuclear Technology / Volume 72 / Number 1 / January 1986 / Pages 59-69

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT86-A33753

Mixed uranium-plutonium monocarbide (MC) with a controlled amount of mixed sesquicarbide (M2C3) will be used as driver fuel for the first time in the world in the fast breeder test reactor (FBTR) at Kalpakkam, India. The mixed-carbide fuel for the FBTR has been developed on the basis of indigenous resources of plutonium and natural uranium and has a plutonium-rich composition [Pu/(U + Pu) = 0.7], The mixed-carbide fuel development and fabrication experience in Trombay is described, highlighting the essential features of the carbide fuel pellet fabrication plant, the carbothermic synthesis of MC from the oxides (UO2 + PuO2), and the sintering of MC.