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The thickness of the interaction layer was about 200 microns for the fuels irradiated at 16 at % burnup. Melting due to the presence of the U6Fe phase is not expected under normal fuel pin operating conditions. However, out-of-pile diffusion tests indicated that the formation of a liquid phase has to be considered for operation under transition conditions where the cladding temperature can reach the 700–800oC temperature range. 31]. The basic results indicate that the cladding failure occur at temperatures near the point of rapid eutectic penetration.

Int. Conf. Versaille, 1995), Vol. I, SFEN, (1995) 538. , et al, “Experimental research on nitride fuel cycle in JAERI”, GLOBAL’99, (Proc. Int. Conf. Jackson Hole, 1999) (CD-ROM). , HEGDE, P. , JAIN, G. C. et. , Development and Fabrication of % PuC – 30 % UC fuel for the Fast Breeder Test Reactor in India, Nucl. Tech. 72 (1986) 59. , “India - Country Report”, Nuclear Fuel Cycle Options, Proc. 2 (1999) 139. , HEGDE, P. , JAIN, G. 45)C fuel pellets for the second core of the Fast Breeder Test Reactor in India, Nucl.

Microstructure and Fission Gas Bubbles in Irradiated Mixed Carbide Fuels at 2 to 11 % Burnup, J. Nucl. Mater. 124 (1984) 159. , “Survey of post-irradiation examinations made of mixed carbide fuels”, Studies on Fuels with Low Fission Gas Release, IAEA-TECDOC-970 (1997) 93. , ‘‘Plutonium 1965’’, eds. KAY, A. , WALDRON, M. , Inst. Metals (Chapman and Hall, London, 1967), 888. 78] FRENCH, P. , HODKIN, D. , Plutonium 1965, eds. , WALDRON, M. , Inst. Metals (Chapman and Hall, London, 1967), 697. , The Sodium-Bonding Pin Concept for Advanced Fuels.

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