Thermodynamic analysis of mixed carbide, carbonitride and nitride fuels for fast breeder reactors
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference23 articles.
1. Development and Fabrication of 70% PuC–30% UC Fuel for the Fast Breeder Test Reactor in India
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4. The Chemical Thermodynamics of Actinides Elements and Compounds, Part 6: Actinide Carbides,1984
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