Three series of investigations of the radiation creep of modified uranium dioxide with grain size ≥25 μm were conducted, using methods and experimental means developed in this work, for reactor conditions at fission density 1.2 · 1013 sec–1 · cm–3. Diagrams of radiation creep in the stress interval 10–40 MPa were obtained for three temperatures. At 747 °C, the results are identical to the radiation creep of standard uranium dioxide. At this temperature, the deformation is controlled by radiation creep, which is confirmed by the linear dependence on the stress. The creep rates at 927 and 1028 °C are higher than for standard uranium dioxide. The stress dependence of the creep rate can be represented by a power-law function or a combination of linear and power-law functions.
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References
V. B. Malygin, K. V. Naboichenko, A. S. Shapovalov, and Yu. K. Bibilashvili, “Recommendations for calculating the radiation creep rate of oxide fuel when analyzing the serviceability of fuel elements,” At. Énerg., 108, No. 2, 95–98 (2010).
OCT95 10261–87, Reactor and Bench Tests: Methods for Mechanical Tests of Nuclear Fuel.
T. B. Ashrapov, V. B. Malygin, K. V. Pavlii, et al., “Complex of experimental means for studying the mechanical properties of nuclear fuel in high-flux reactors,” Experimental Support for Reactor Tests of Materials, Energoatomizdat, Moscow (1990), pp. 49–54.
A. G. Samoilov, V. S. Volkov, and V. M. Solonin, Fuel Elements for Nuclear Reactors, Energoatomizdat, Moscow (1996).
A. Evans and R. Davidge, “The strength and fracture of stoichiometric polycrystalline UO2,” J. Nucl. Mater., 33, 249–260 (1969).
ANSYS 7.0 Documentation, Thermal Analysis Guide, ANSYS Inc. Release 12.1, Nov. 2009.
V. B. Malygin, A. S. Shapovalov, E. N. Mikheev, et al., RF Patent 117701, G21D 1/100, “Setup for studying the radiation creep of nuclear fuel of power reactors,” Byull. Izobr. Polez. Modeli, No. 18, 202 (2012).
GOST 22388–90, Single-Layer Bellows with Diameter to 200 mm. General Technical Conditions.
GOST R 8.585–2001, Thermocouples. Nominal Static Conversion Characteristics.
V. B. Malygin, V. N. Remezov, A. A. Silin, et al., “Colligation of experience in operating motion transducers during in-channel studies,” Tests of Reactor Materials, Energoatomizdat, Moscow (1988), pp. 34–36.
LabView Professional Development System, National Instruments Ltd. (2013).
A. V. Kuleshov, V. V. Novikov, E. N. Mikheev, et al., RF Patent 2376665, G21C 3/62, “Pellet of high-burnup nuclear fuel and method of fabricating it,” Byull. Izobr. Polez. Modeli, No. 35, 885–886 (2009).
V. B. Malygin, K. V. Naboichenko and M. G. Sulaimonov, “Analysis of experimental results on radiation creep in the presence of radial and axial gradients of temperatures and fission densities,” Techniques of Reactor Experiments, Energoatomizdat, Moscow (1985), p. 93.
J. Perrin, “Effect of irradiation on creep of UO2–PuO2,” J. Nucl. Mater., 42, 101–104 (1972).
D. Brucklacher and W. Dienst, “Creep behaviour of ceramic nuclear fuels under neutron irradiation,” ibid., pp. 285–289.
A. Solomon, “Irradiation induced creep of UO2,” J. Am. Cer. Soc., 56, No. 3, 164–171 (1973).
E. Sykes and P. Sawbridge, Irradiation Induced Creep of Uranium Dioxide: Tech. Report RD/B/M-1489, Nov., 1969.
J. Perrin, “Irradiation induced creep of uranium dioxide,” J. Nucl. Mater., 39, 175–179 (1971).
Yu. V. Bozhko, V. B. Malygin, Yu. V. Miloserdin, and K. V. Naboichenko, “High-temperature plasticity of uranium dioxide,” Vopr. At. Nauki Tekhn. Ser. At.-Vodor. Energet. Tekhn., No. 1(11), 75–77 (1982)
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Translated from Atomnaya Énergiya, Vol. 116, No. 1, pp. 15–20, January, 2014.
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Mikheev, E.N., Fedotov, A.V., Novikov, V.V. et al. Methodology and Results of Investigation of Radiation Creep in Large-Grain Uranium Dioxide Based Fuel. At Energy 116, 20–26 (2014). https://doi.org/10.1007/s10512-014-9811-6
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DOI: https://doi.org/10.1007/s10512-014-9811-6