| Autor: |
Proksch, Emil, Strigl, Anton, Nabielek, Heinz |
| Zdroj: |
Journal of Nuclear Materials; June 1982, Vol. 107 Issue: 2-3 p280-285, 6p |
| Abstrakt: |
Mass-spectrometric measurements of CO contained in irradiated UO2kerneled HTR fuel particles are summarized and evaluated. The oxygen release O/F (atoms per fission) at the end of irradiation is found to be a function of irradiation time t(days) and irradiation temperature T(particle surface temperature, °C); no dependence upon the type of nuclide fissioned (uranium or plutonium) could be found. Within the limits of 66 < t< 550 days, 950 < T< 1525°CandO/F<0.40 fU+ 0.85 fPu(fU, fPuare the fractions of fissions in uranium and plutonium, respectively) the oxygen release can be represented by the empirical expression log{(O/F)/t2} = −0.21–8500/(T+ 273). |
| Databáze: |
Supplemental Index |
| Externí odkaz: |
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