The results of an investigation of the release of the radioactive fission products 85Kr and 137Cs from dioxide and mononitride nuclear fuel irradiated in the BN-600 and BR-10 fast reactors are presented. The investigation of highly active fuel samples was performed on a remote experimental setup placed in a hot chamber. It is shown that for almost the same annealing temperatures and times of the irradiated samples the release of both fission products – 85Kr and volatile fission product 137Cs – from dioxide fuel is approximately 2 times higher than from mononitride fuel. The 85Kr and 137Cs are released from irradiated uranium dioxide in three thermally activated stages, which for 137Cs are shifted by 89–330°С toward lower temperatures with respect to 85Kr.
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J. Hiernaut, T. Wiss, J. Colle, et al., Fission product release and microstructure change during laboratory annealing of a very high burn-up fuel specimen,” J. Nucl. Mater., 377, 313–324 (2008).
J. Hiernaut and C. Ronchi, “Fission gas release and volume diffusion enthalpy in UO2 irradiated at low and high burnup,” J. Nucl. Mater., 294, 39–44 (2001).
J. Colle, J. Hiernaut, D. Papaioannou, et al., “Fission product release in high-burn-up UO2 oxidized to U3O8,” J. Nucl. Mater., 348, 229–242 (2006).
C. Ronchi and J. Hiernaut, “Helium diffusion in uranium and plutonium oxides,” J. Nucl. Mater., 325, 1–12 (2004).
S. V. Zabrodskaya, L. I. Moseev, V. M. Poplavskii, et al., “Experimental and computational study of the release of radioactive products from the irradiated fuel of a fast sodium reactor,” At. Energ., 124, No. 2, 80–86 (2018).
S. I. Porollo, S. N. Ivanov, E. E. Marinenko, et al., “Analysis of experimental data on gas evolution and swelling of mononitride uranium fuel irradiated in the BR-10 reactor,” At. Energ., 121, No. 6, 326–332 (2016).
A. F. Grachev, L. M. Zabudko, Yu. A. Ivanov, et al., “Results of a study of BN-600 fuel elements with mixed uranium-plutonium nitride fuel and a cladding made of ChS68-ID c.d. Steel,” At. Energ., 126, No. 3, 160–166 (2019).
D. Yu. Lyubimov, I. A.Deryabin, G. S. Bulatov, et al., “Thermodynamic modeling of the phase composition of mixed uranium-plutonium mononitride with an admixture of oxygen under irradiation up to burnup 140 GW·day/t and temperature 900–1400 K,” At. Energ., 118, No. 1, 24–29 (2015).
R. Thetford and M. Mignanelli, “The chemistry and physics of modelling nitride fuels for transmutation,” J. Nucl. Mater., 320, 44–53 (2003).
Translated from Atomnaya Énergiya, Vol. 130, No. 2, pp. 74–78, February, 2021.
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Porollo, S.I., Moseev, L.I. & Konobeev, Y.V. Investigation of Fission Product Release from Irradiated Oxide and Nitride Nuclear Fuel on High-Temperature Heating in Helium Flow. At Energy 130, 76–81 (2021). https://doi.org/10.1007/s10512-021-00777-w