85Kr release during the oxidation and self-heating of irradiated uranium in air

作者: D.A. Hilton

DOI: 10.1016/0022-3115(70)90158-3

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摘要: Abstract The behaviour of the fission gas 85 Kr has been studied during oxidation irradiated uranium in air. Over temperature range 220–320 °C there is a direct proportionality between extent isothermal and amount released. Above 300 metal can self heat although well defined ignitions do not occur thermal cycling reaction observed, which with unirradiated initiated at least 200 higher. During release curve follows considerable sensitivity curve. degree heating insufficient for bubble growth to play significant role it concluded that solid product concentration oxide stoichiometry are important parameters initiation continuation reactions.

参考文章(9)
Walter D. Wilkinson, Uranium corrosion and alloys Interscience Pub.. ,(1962)
L. Baker, J.D. Bingle, The kinetics of oxidation of uranium between 300 and 625° C Journal of Nuclear Materials. ,vol. 20, pp. 11- 21 ,(1966) , 10.1016/0022-3115(66)90017-1
R.J. Pearce, I. Whittle, D.A. Hilton, The oxidation of uranium in carbon dioxide and carbon monoxide (A review) Journal of Nuclear Materials. ,vol. 33, pp. 1- 16 ,(1969) , 10.1016/0022-3115(69)90002-6
R. Scott, A.R. Hall, J. Williams, The plastic deformation of uranium oxides above 800° C Journal of Nuclear Materials. ,vol. 1, pp. 39- 48 ,(1959) , 10.1016/0022-3115(59)90009-1
D.F. Fischer, J.G. Schnizlein, The ignition of irradiated uranium Journal of Nuclear Materials. ,vol. 28, pp. 124- 128 ,(1968) , 10.1016/0022-3115(68)90066-4
J.G. Schnizlein, L. Baker, J.D. Bingle, The ignition of binary alloys of uranium Journal of Nuclear Materials. ,vol. 20, pp. 39- 47 ,(1966) , 10.1016/0022-3115(66)90019-5
R. K. Hilliard, C. E. Linderoth, A. J. Scott, Fission product release from overheated uranium--a laboratory study. Health Physics. ,vol. 7, pp. 1- 10 ,(1961) , 10.1097/00004032-196111000-00001
G. Christie, J. Williams, The effect of small additions of yttria on the plasticity of uranium oxides at 940° C Journal of Nuclear Materials. ,vol. 5, pp. 1- 4 ,(1962) , 10.1016/0022-3115(62)90035-1