Abstract
The results of development work on a new generation of fuel elements based on microfuel for VVÉR reactors using the basic data from post-reactor investigations and bench tests in experiments simulating LOCA for existing fuel elements with ceramic fuel are presented. It is shown that cermet fuel elements will make it possible to realize most fully the advantages of such fuel, specifically, to develop a sealed first loop and to simplify and reduce the cost of safety, automatic control, radiation protection, coolant puification, and other systems. For example, cermet fuel elements in VVÉR-1500 reactors can improve safety under various operating conditions, maneuverability, vibrational strength, fuel assembly lifetime, and geometric stability of fuel elements.
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REFERENCES
P. I. Lavrenyuk, B. A. Vasil'ev, G. L. Lunin, et al., "Fuel for nuclear power plants. Status and prospects," in: 3rd Scientific Conference of the Russian Ministry of Atomic Energy "Atomic Energy. Status and Prospects,"Moscow (2002), pp. 160–177.
B. I. Nigmatullin and V. V. Severinov, "Role, potential, and conditions of dynamic development of nuclear power plants," ibid.}, pp. 5–14.
A. S. Chernikov, L. N. Permyakov, and S. S. Gavrilin, "Fuel element with cermet fuel of matrix type for VVÉRs of enhanced safety," in: 7th International Conference on Emerging Nuclear Energy Systems, September 20-24, 1993, Nakuhari, Japan.
A. S. Chernikov, L. N. Permyakov, I. I. Fedik, et al., "Fuel elements based on spherical particles with a protective coating for enhanced-safety reactors," At. Énerg., 87, No. 6, 451–462 (1999).
V. B. Ivanov, "Scientific and technical problems of the nuclear fuel cycle," in: Scientific Conference of the Russian Ministry of Atomic Energy on the Nuclear Fuel Cycle,June 2000, Moscow, pp. 3–16.
V. A. Tsykanov, V. Ya. Vasil'ev, G. I. Gadzhiev, et al., Review of the Main Research Work Performed at the Scientific-Research Institute of Nuclear Reactors in 1994, Dimitrovgrad (1995), pp. 52–58. 258
M. I. Solonin, F. G. Reshetnikov, A. G. Ioltukhovskii, and A. V. Nikulina, "New structure materials for nuclear reactor cores," in: Selected Works of the All-Russia Scientific-Research Institute for Standardization in Machine Engineering (2002), Vol. 1, pp. 84–101.
V. V. Makarov, "Fretting-corrosion of fuel-element cladding in spacing lattices of VVÉR-1000 fuel assemblies," Vopr. At. Nauk. Tekh., Ser. Obespech. Bezopas. AÉS. Reaktor. Ustan. VVÉR, No. 1, 33–39 (2002).
M. I. Solonin, Yu. K. Bibilashvili, A. V. Nikulina, et al., "Zirconium-niobium alloys for fuel-element cladding and fuel assemblies for VVÉR and RBMK power reactors and systems," in: Selected Works of the All-Russia Scientific-Research Institute for Standardization in Machine Engineering (2002), Vol. 1, pp. 65–83.
A. S. Chernikov, L. N. Permyakov, and S. S. Gavrilin, "Cermet fuel elements for VVERs," in: Proceedings of ARS'94 International Topical Meeting on Advanced Reactor Safety, Pittsburgh, USA (1994), Vol. 2, pp. 1097–1101.
F. G. Reshetnikov, Yu. K. Bibilashvili, I. S. Golovin, et al., "Problems of developing VVÉR-1000 fuel elements for operation under the conditions of maneuverable nuclear powr plants and enhanced burnup," At. Énerg., 64, No. 4, 258–267 (1988).
P. G. Afanas'ev, V. S. Konstantinov,, P. V. Kozlobaev, et al., "Experimental investigations of the behavior of fuel element simulators in model VVÉR fuel assemblies on the Parametr-M bench under conditions simulating various stages of an accident with a large leak," in: Collection of Works of the Scientific-Research Institute and Scientific-Industrial Association Luch (2000-2002), pp. 69–80.
V. P. Deniskin, V. S. Konstantinov, V. I. Nalivaev, et al., "Parametr bench simulation of the behavior of VVÉR fuel elements at the first stage of a maximum anticipated accident," in: Abstracts of Reports at the 3rd Scientific and Technical Conference on Guaranteeing the Safety of Nuclear Power Plants with VVÉR Reactors, May 26-30, 2003, Podol'sk, pp. 52–53.
Yu. K. Bibilashvili, N. B. Sokolov, L. N. Andreeva-Adrievskaya, et al., "Termomechanical properties of oxidized zirconium-alloy fuel-element cladding under the conditions of a loss-of-coolant accident," in: Selected Works of the All-Russia Scientific-Research Institute for Standardization in Machine Engineering (2002), Vol. 1, pp. 221–239.
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Fedik, I.I., Gavrilin, S.S., Deniskin, V.P. et al. New Generation of Microfuel-Based Fuel Elements for VVÉR Reactors. Atomic Energy 96, 250–259 (2004). https://doi.org/10.1023/B:ATEN.0000035995.94259.dd
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DOI: https://doi.org/10.1023/B:ATEN.0000035995.94259.dd