Abstract
The characteristic properties of hardened single-crystal alloys (Mo-Nb, W-Nb, W-Ta) and UO2-x with open thermally stabilized porosity are presented. The combination of the indicated materials makes thermionic fuel elements very stable with a long service life. It is shown that the use of porous uranium dioxide under temperature conditions resulting in restructuring makes it possible to decrease the size of the columnar grains and increase the creep rate of the dioxide with optimal porosity and pore size. A model oxide fuel, which has been developed, with fission-product simulators for rapid determination under extra-reactor conditions of the properties of uranium with deep burnup and for performing accelerated reactor tests is described.
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REFERENCES
Yu. V. Nikolaev, A. A. Yastrebov, A. S. Gontar', et al., “Basic materials and technologies for prolonged service life and efficiency of electricity generating channels,” in: Collection of Works of the Scientific-Research Institute and Scientific and Industrial Association Luch for 2000–2002, TSNIIatominform, Moscow (2003), pp. 24–28.
Yu. V. Nikolaev, V. S. Kolesov, P. V. Zubarev, et al., “Molybdenum and tungsten single crystal alloys with abnormally high creep strength for space nuclear power and propulsion systems,” in: Proceedings of the 10th Symposium on Space Nuclear Power and Propulsion Systems, Albuquerque (1993), Part 1, pp. 267–274.
A. S. Gontar', “Improved single-element electricity generating channel for thermionic nuclear power systems with high capacity,” in: Abstracts of Reports at the International Conference on Nuclear Power in Space — 2005, NIKIET, Moscow (2005), p. 36.
A. I. Evstyukhin, I. I. Gavrilov, V. P. Smirnov, et al., “Production of single-crystal precipitates of W from chlorides using transport reactions,” in: Single Crystals of Refractory and Rare Metals, Alloys, and Compounds, Nauka, Moscow (1977), pp. 27–32.
A. S. Gontar, R. Ya. Kucherov, Yu. V. Nikolaev, et al., “Merits of the refractory metals single crystals in application to the TFE,” in: Proceedings of the 31 Intersociety Energy Conversion Engineering Conference, Washington (1996), Vol. 2, pp. 951–956.
B. N. Varaksin and A. S. Titkov, “Experimental investigation of a thermionic energy converter in the arc regime with different tungsten emitters,” Zh. Tekhn. Fiz., 46, No.8, 1665–1669 (1976).
E. M. Savitskii and G. S. Burkhanov, Single Crystals of Refractory and Rare Metals and Alloys, Nauka, Moscow (1972), pp. 233–236.
V. S. Gutnik, E. M. Rakitskaya, and V. L. Tsyplenkova, “High-density uranium dioxide: some properties,” in: Proceedings of the Report of the 4th Industrial Conference on Nuclear Power in Space. Materials. Fuel, Podol'sk (1993), p. 261.
E. M. Rakitskaya, V. I. Babin, A. S. Gontar', et al., “Modified uranium dioxide,” ibid., p. 73.
Yu. G. Degal'tsev, A. S. Gontar', V. F. Kuznetsov, et al., “Post-reactor investigations of processes in uranium dioxide fuel for a single-element thermionic energy converter,” in: Abstracts of Reports at the Industrial Anniversary Conference on Nuclear Power in Space, Obninsk (1990), Part 1, pp. 207–210.
Yu. G. Degal'tsev, V. F. Kuznetsov, and N. N. Ponomarev-Stepnoi, “Physical and mathematic model of swelling of high-temperature fuel element with ceramic fuel,” Preprint IAE-5250/11 (1990).
A. S. Gontar', V. S. Gutnik, V. A. Zaitsev, et al., “Method and results of comparative radiation tests of high-temperature fuel materials,” in: Abstracts of Reports at the 4th Industrial Conference on Nuclear Power in Space. Materials. Fuel, Podol'sk (1993), pp. 81–82.
A. A. Gridnev, D. N. Dzhalandinov, P. V. Zubarev, and A. S. Panov, “Investigation of high-temperature creep of large-grain uranium dioxide,” At. Energ., 59, No.1, 27–29 (1985).
A. Bauer, “A model for the high temperature swelling of clad oxide fuel,” Nucl. Tech., 13, 65–70 (1972).
Yu. V. Nikolaev, D. Yu. Lyubimov, A. S. Panov, et al., “Extra-reactor simulation of the state of uranium dioxide with deep burnup,” in: Abstracts of Reports at the 4th Interdisciplinary Conference on Reactor Materials Engineering, Dimitrovgrad (1995), pp. 58–59.
A. S. Popov, E. M. Rakitskaya, Yu. K. Bibilashvili, et al., “Influence of fission products on the properties of oxide fuel,” in: Abstracts of Reports at the 5th International Conference on Nuclear Power in Space, Podol'sk (1999), p. 60.
A. S. Gontar', V. S. Gutnik, M. V. Nelidov, and A. S. Panov, “Accelerated tests of fuel materials for an energy generating channel,” in: Abstracts of Reports at the 2nd International Seminar on Space Nuclear Power Production in the 21st Century SNPE-XXI, Obninsk (2000), p. 52.
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Translated from Atomnaya Energiya, Vol. 99, No. 5, pp. 365–371, November, 2005.
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Gontar', A.S., Nelidov, M.V., Nikolaev, Y.V. et al. Structural and Fuel Materials for the Fuel Elements of Thermionic Nuclear Power Systems. At Energy 99, 799–805 (2005). https://doi.org/10.1007/s10512-006-0019-2
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DOI: https://doi.org/10.1007/s10512-006-0019-2