Densification behaviour and sintering kinetics of (U0.45Pu0.55)C pellets

Author:

Kutty T.R.G.,Khan K.B.,Kutty P.S.,Basak C.B.,Sengupta A.K.,Mehrotra R.S.,Majumdar S.,Kamath H.S.

Publisher

Elsevier BV

Subject

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

Reference20 articles.

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

2. Evaluation of phases in Pu-C-O and (U, Pu)-C-O systems by X-ray diffractometry and chemical analysis

3. C. Ganguly, Studies on the preparation and sintering of mixed uranium–plutonium mixed monocarbide, mononitride and monocarbonitride, PhD thesis, University of Calcutta, 1980

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

5. Science of Advanced LMFBR Fuels: A Monograph on Solid State Physics, Chemistry and Technology of Carbides, Nitrides and Carbonitrides of Uranium and Plutonium;Matzke,1986

Cited by 4 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献

1. C-Pu-U Ternary Phase Diagram Evaluation;MSI Eureka;2019-11-12

2. Interatomic potentials for PuC by Chen–Möbius multiple lattice inversion;Journal of Nuclear Materials;2013-11

3. Rate Controlled Sintering: A Unique Concept for Microstructural Control;Transactions of the Indian Ceramic Society;2007-10

4. C-Pu-U (Carbon-Plutonium-Uranium);Non-Ferrous Metal Systems. Part 4;2007

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