A model for the effect of the progression of irradiation-induced recrystallization from initiation to completion on swelling of UO2 and U-10Mo nuclear fuels
暂无分享,去创建一个
[1] G. L. Hofman,et al. POST-IRRADIATION ANALYSIS OF LOW ENRICHED U-Mo/A1 DISPERSIONS FUEL MINIPLATE TESTS, RERTR 4 & 5 , 2005 .
[2] Donald R. Olander,et al. Fundamental Aspects of Nuclear Reactor Fuel Elements , 1976 .
[3] Gerard L. Hofman,et al. An alternative explanation for evidence that xenon depletion, pore formation, and grain subdivision begin at different local burnups , 2000 .
[4] D. Kuhlmann-wilsdorf,et al. Low energy dislocation structures due to unidirectional deformation at low temperatures , 1986 .
[5] M. Coquerelle,et al. Detailed characterisation of the rim microstructure in PWR fuels in the burn-up range 40–67 GWd/tM , 1996 .
[6] Effect of grain size on recrystallization in high burnup fuel pellets , 1997 .
[7] H. Matzke,et al. Gas release mechanisms in UO2—a critical review , 1980 .
[8] J. Rest,et al. The effect of irradiation-induced gas-atom re-solution on grain-boundary bubble growth , 2003 .
[9] J. Rest,et al. A model for the influence of microstructure, precipitate pinning and fission gas behavior on irradiation-induced recrystallization of nuclear fuels☆ , 2004 .
[10] M. Wood,et al. On the in-pile nucleation and growth of grain-boundary bubbles , 1983 .