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    • Mixed plutonium-uranium carbide fuel in fast breeder test reactor

      P Rodriguez

      Ceramics And Glasses Volume 22 Issue 3 May 1999 pp 215-220

    • Fulltext

       

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      Permanent link:
      https://www.ias.ac.in/article/fulltext/boms/022/03/0215-0220

    • Keywords

       

      Nuclear fuel; fast reactors; carbides

    • Abstract

       

      This paper describes the development of the indigenous plutonium-uranium mixed carbide nuclear fuel for the fast breeder test reactor. The fuel has performed satisfactorily and produced, for the first time in our country, nuclear electricity from a fast reactor. The experience and knowledge gained in the fuel development has provided great confidence for undertaking a programme on utilization of fast reactor technology for power production.

    • Author Affiliations

       

      P Rodriguez1

      1. Indira Gandhi Centre for Atomic Research, Kalpakkam - 603 102, India

    • Dates

       
      Published
      May 1999

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