Experience on mixed carbide fuels with high ‘Pu’ content for Indian fast breeder reactor – An overview

Author:

Sengupta A.K.,Basak U.,Kumar Arun,Kamath H.S.,Banerjee S.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference29 articles.

1. M. Housseau, G. Dean, F. Perret, in: Proceedings of the International Conference on “Behaviour and Chemical State of Irradiated Ceramic Fuels”, Vienna, 7–11 August 1972, p. 349.

2. Hot hardness of hyperstoichiometric mixed uranium plutonium monocarbide

3. Out-of-Pile Properties of Hyperstoichiometric (U0.45Pu0.55)C Fuel for the Fast Breeder Test Reactor

4. Preparation, characterisation and out-of-pile property evaluation of (U,Pu)N fuel pellets

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