The sintering of grain boundary cavities in uranium dioxide
作者： B. Burton , G.L. Reynolds
DOI: 10.1016/0022-3115(72)90107-9
关键词:
摘要: Abstract The final stage sintering of uranium dioxide has been investigated in the temperature range 1623–1973 K where residual porosity is situated mainly on grain boundaries. shape curve quantitatively predicted from a knowledge cavity distribution and rate an individual described by Hull Rimmer (1959) equation. effective grain-boundary diffusion coefficient estimated these curves shown to be reasonable agreement with measured radio-tracer methods. effect entrapped gas appears negligible importance since cavities were observed sinter closure; neither did growth strongly affect rates, remained
harvard.edu
osti.gov
elsevier.com
sci-hub.se 参考文章(5)
A.B. Auskern, J. Belle, Uranium ion self diffusion in UO2 Journal of Nuclear Materials. ,vol. 3, pp. 311- 319 ,(1961) , 10.1016/0022-3115(61)90199-4
W. B. Beere, G. W. Greenwood, The Effect of Hydrostatic Pressure on the Shrinkage of Cavities in Metals Metal Science Journal. ,vol. 5, pp. 107- 113 ,(1971) , 10.1179/030634571790439757
S. Yajima, H. Furuya, T. Hirai, Lattice and grain-boundary diffusion of uranium in UO2 Journal of Nuclear Materials. ,vol. 20, pp. 162- 170 ,(1966) , 10.1016/0022-3115(66)90004-3
R.M. Cornell, J.A. Turnbull, The nucleation of bubbles and re-solution effects in uranium dioxide irradiated at elevated temperatures Journal of Nuclear Materials. ,vol. 41, pp. 87- 90 ,(1971) , 10.1016/0022-3115(71)90201-7
J.P. Marin, Estimation des energies d'activation de diffusion intergranulaire de l'uranium dans le dioxyde surstoechiometrique UO2 + x Journal of Nuclear Materials. ,vol. 34, pp. 348- 350 ,(1970) , 10.1016/0022-3115(70)90205-9