Microstructure and fission gas bubbles in irradiated mixed carbide fuels at 2 to 11 a/o burnup
暂无分享,去创建一个
H. Blank | I.L.F. Ray | H. Blank | I. Ray
[1] C. Baker,et al. The migration of intragranular fission gas bubbles in irradiated uranium dioxide , 1977 .
[2] J. Gilman. Propagation of Cleavage Cracks in Crystals , 1956 .
[3] B. Eyre,et al. On the formation and behaviour of point defect clusters in neutron irradiated uranium carbide , 1966 .
[4] M. Whelan,et al. Investigations of dislocation strain fields using weak beams , 1969 .
[5] M. Coquerelle,et al. The Sodium-Bonding Pin Concept for Advanced Fuels Part I: Swelling of Carbide Fuel up to 12% Burnup , 1983 .
[6] C. Baker. The fission gas bubble distribution in a mixed oxide fast reactor fuel pin , 1978 .
[7] Donald R. Olander,et al. Fundamental Aspects of Nuclear Reactor Fuel Elements , 1976 .
[8] R. Ham. The determination of dislocation densities in thin films , 1961 .
[9] C. Ronchi,et al. Swelling analysis of highly-rated MX-type LMFBR fuels: II. Microsopic swelling behaviour , 1978 .
[10] M. Makin,et al. The nature of fission fragment tracks in uranium dioxide , 1962 .
[11] Eal H. Lee,et al. Precipitation and cavity formation in austenitic stainless steels during irradiation , 1981 .
[12] C. Baker,et al. The fission gas bubble distribution in uranium dioxide from high temperature irradiated sghwr fuel pins , 1977 .