[1] C.T. Walker, T. Kameyama, S. Kitajima, M. Kinoshita, Concerning the microstructure changes that occur at the surface of UO2 pellets on irradiation to high burnup, J. Nucl. Mater., 188 (1992) 73-79.
[2] J.C. Killeen, Fission gas release and swelling in UO2 doped with Cr2O3, J. Nucl. Mater., 88 (1980) 177-184.
[3] H. Assman, W. Dorr, Microstructure and density of UO2 pellets for light water reactors as related to powder properties, Ceramic powders, Edited by P. Vincenzini. Elsevier Scientific Publishing company, Amsterdam, (1983) 707-718.
[4] K. Une, I. Tanabe, M. Oguma, Effects of Additives and the oxygen potential on the fission gas diffusion in UO2 fuel, J. Nucl. Mater., 150 (1987) 93-99.
[5] L. Bourgeois, P. Dehaudt, C. Lemaignan, J.P. Fredric, Pore migration in UO2 and grain growth kinetics, J. Nucl. Mater., 295 (2001) 73-82.
[6] S. Kashibe, K. Une, Effect of additives (Cr2O3, Al2O3, SiO2, MgO) on diffusional release of 133Xe from UO2 fuels, J. Nucl. Mater., 254 (1998) 234-242.
[7] P.T. Sawbridge, C. Baker, R.M. Cornell, K.W. Jones, D. Reed, J.B. Ainscough, The irradiation performance of magnesia-doped UO2 fuel, J. Nucl. Mater., 95 (1980) 119-128.
[8] H. Assmann, W. Doerr, M. Peehs, Oxide fuels with controlled microstructure, J. Am. Ceram. Soc., 67[9] (1984) 631-636.
[9] R.N. Singh, Isothermal grain- growth kinetics in sintered UO2 pellets, J. Nucl. Mater., 64 (1977) 174-178.
[10] Letter to the editors, Grain growth in high density UO2, J. Nucl. Mater., 148 (1987) 351-352.
[11] W.I. Stuart, R.B. Adams, Effects of sintering atmosphere on the density of uranium dioxide pellets, J. Nucl. Mater., 58 (1975) 201-204.
[12] P. Balakrishna, B.N. Murty, K.P. Chakraborthy, R.N. Jayaraj, C. Ganguly, Coarsening- densification transition temperature in sintering of uranium dioxide, J. Nucl. Mater., 297 (2001) 35-42.
[13] L. Bourgeois, P. Dehaudt, C. Lemaignan, A. Hammou, Factors governing microstructure development of Cr2O3-doped UO2 during sintering, J. Nucl. Mater., 297 (2001) 313-326.
[14] K.S. Kim, K.W. Song, J.H. Yang, K.W. Kang, Y.H. Jung, Sintering behavior of Cr2O3-doped UO2 pellets, J. Kore. Nucl. Soc., 35[1] (2003) 14-24.
[15] T.B. Lindemer, T.M. Besman, Chemical thermodynamic representation of < UO2±x>, J. Nucl. Mater., 130 (1985) 473-488.
[16] H. Assmann, W. Dorr, M. Peehs, Control of UO2 microstructure by oxidative sintering, J. Nucl. Mater., 140 (1986) 1-6.
[17] F. Glodeanu, M. Spinzi, V. Balan, Correlation between UO2 Powder and pellet quality in PHWR fuel manufacturing, J. Nucl. Mater., 153 (1988) 156-159.
[18] T.R.G. Kutty, P.V. Hegde, K.B. Khan, S. Majumdar, D.S.C. Purushotham, Sintering studies on UO2-PuO2 pellets with varying PuO2 content using dilatometry, J. Nucl. Mater., 282 (2000) 54-65.
[19] K.W. Song, K.S. Kim, Y.M. Kim, Y.H. Jung, Sintering of mixed UO2 and U3O8 powder compacts, J. Nucl. Mater., 277 (2000) 123-129.
[20] Y.W. Lee, M.S. Yang, Characterization of HWR fuel fabricated using UO2 powders from different Conversion processes, J. Nucl. Mater., 178 (1991) 217-226.
[21] P. Das, R. Chowdhury, Studies on the sintering behavior of Uranium dioxide powder Compacts, J. Nucl. Mater., 158 (1988) 61-266.
[22] J.B. Aiscouch, F. Rigby, The effect of magnesia on the grain structure of sintered uranium dioxide, Ceramic powders, Edited by P. VinCenzini. Elsevier Scientific Publishing company, Amsterdam, (1983) 921-927.
[23] K.C. Radford, J.M. Pope, UO2 fuel pellet microstructure modification through impurity additions, J. Nucl. Mater., 116 (1983) 305-313.
[24] L. Mazeina, A. Navrotsky, M. Greenblatt, Calorimetric determination of energetics of solid solutions of UO2+x with CaO and Y2O3, J. Nucl. Mater., 373 (2008) 39–43.
[25] R. Massih, Effects of additives on uranium dioxide fuel behavior, Quantum Technologies AB, Uppsala, Sweden, 2014.
[26] N.Y. TOKER, L.S. DARKEN, A. MUAN, Equilibrium Phase Relations and Thermodynamics of the Cr-O System in the Temperature Range of 1500˚C to 1825˚C, Metallurg. Transact. B, 22B (1991) 225-232.
[27] J.H. Yang, K.S. Kim, I.H. Nam, J.S. Oh, D.J. Kim, Y.W. Rhee, J.H. Kim, Effect of step wise variation of oxygen potential during the isothermal sintering on the grain growth behavior in Cr2O3 doped UO2 pellets, J. Nucl. Mater., 429 (2012) 25–33.
[28] T. Cardinaels, K. Govers, B. Vos, S.V.d. Berghe, M. Verwerft, L.d. Tollenaere, G. Maier, C. Delafoy, Chromia doped UO2 fuel: Investigation of the lattice parameter, J. Nucl. Mater., 424 (2012) 252–260.
[29] R.A. Rahimi, M. Iravani, M. Mohammadifar, Study on swelling caused by fission products in UO2 nuclear fuel pellets, Final project report, Material Research School, Nuclear Science and
Technology Research Center, (1391).
[30] R.A. Rahimi, M. Iravani, M. Mohammadifar, Research and study the factors affecting the increase of burn up of UO2 pellets, Final project report, Material Research School, Nuclear Science and Technology Research Center, (1391).