Conclusions
A complex procedure has been developed for the study of gas release from nuclear fuel, including reactor measurements and post-reactor determination of the amount and composition of the gas medium in the fuel elements at room and elevated temperatures. In fuel elements with compact uranium dioxide (density 10.0–10.43 g/cm3), in addition to gaseous fission products and the helium introduced, Ar, H2, O2, CO, CO2, and N2 are present, and after irradiation their quantity exceeds the initial quantity, measured for unirradiated fuel elements, by a factor of several.
The yield of Xe and Kr under the can of the fuel elements during irradiation of uranium dioxide in the SM-2 reactor amounts to ∼30–50%, but the measured ratio of Xe/Kr exceeds the calculated ratio by a factor of 1.2, because of the reaction135Xe(n, γ)136Xe. The content in the fuel of adsorbed helium is equal to ∼0.004 n.cm3/g UO2. The data obtained can be used for physics and technological calculations, and also for refining the procedure for the determination of gas release.
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Literature Cited
B. V. Samsonov and V. Sh. Sulaberidze, Analytical Review of the Scientific-Research Institute of Atomic Reactors [in Russian], Vol. 16, Dimitrovgrad (1977).
V. Sh. Sulaberidze et al., Preprint of the Scientific-Research Institute of Atomic Reactors [in Russian], Dimitrovgrad, P-26 (541) (1982).
V. Sh. Sulaberidze and A. V. Pershin, At. Energ.,53, No. 3, 158 (1982).
V. Sh. Sulaberidze and A. V. Pershin, Preprint of the Scientific-Research Institute of Atomic Reactors [in Russian], Dimitrovgrad, P-19(584), (1983).
V. A. Tsykanov et al., Preprint of the Scientific-Research Institute of Atomic Reactors [in Russian], Dimitrovgrad, P-5(271) (1976).
A. P. Kirillovich et al., Preprint of the Scientific-Research Institute of Atomic Reactors [in Russian], Dimitrovgrad, 31(439) (1980).
H. Zimmerman, Nucl. Technol.,28, 127 (1976).
K. Vinjamuri and D. Owen, Nucl. Technol.,47, No. 1, 119 (1980).
V. I. Polikarpov et al., Monitoring the Leak Tightness of Fuel Elements [in Russian], Gosatomizdat, Moscow (1962).
Additional information
Translated from Atomnaya Énergiya, Vol. 57, No. 2, pp. 91–95, August, 1984.
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Kirillovich, A.P., Sulaberidze, V.S., Pimonov, Y.I. et al. Gas phase in experimental fuel elements with compact uranium dioxide, irradiated in the SM-2 reactor. At Energy 57, 517–522 (1984). https://doi.org/10.1007/BF01123751
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DOI: https://doi.org/10.1007/BF01123751