Published January 1986
| Version v1
Journal article
Development and fabrication of 70% PuC-30% UC fuel for the fast breeder test reactor in India
- 1. Bhabha Atomic Res. Centre, Radiometallurgy Div., Bombay 400 085
Description
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
Additional details
Publishing Information
- Journal Title
- Nucl. Technol.
- Journal Volume
- 72
- Journal Issue
- 1
- Series
- Nucl. Technol.
- Journal Page Range
- vp
- ISSN
- 0029-5450
- CODEN
- NUTYB
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17049966
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- FABRICATION; FBR TYPE REACTORS; FUEL FABRICATION PLANTS; INDIA; MIXED CARBIDE FUELS; NATURAL URANIUM; PLUTONIUM CARBIDES; PLUTONIUM DIOXIDE; QUANTITY RATIO; SINTERING; URANIUM CARBIDES; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; ASIA; BREEDER REACTORS; CARBIDES; CARBON COMPOUNDS; CHALCOGENIDES; DEVELOPING COUNTRIES; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FUELS; MATERIALS; METALS; NUCLEAR FACILITIES; NUCLEAR FUELS; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM OXIDES; REACTOR MATERIALS; REACTORS; SOLID FUELS; TRANSURANIUM COMPOUNDS; URANIUM; URANIUM COMPOUNDS; URANIUM OXIDES