Prospective Micro-Encapsulated Fuel with Silicon Carbide Protective Coat
A promising direction in the development of the next-generation fuel is the development of fully ceramic micro-encapsulated fuel (FCM). Such fuel has proven itself well in high-temperature gas-cooled reactors (HTGR). The fuel consists of 200–700 μm in diameter microspheres made from the fuel material coated with a multi-layer ceramic coating. The standard four-layer coating used in HTGR reactors consists of three layers of pyrolytic carbon and a layer of silicon carbide. The technology developed at VNIINM for fabricating protective coatings consisting of only silicon carbide makes it possible to enhance the radiation and heat resistance of the coatings and, correspondingly, increase the fuel life. Calculations have confirmed the main advantages of the micro-encapsulated fuel with a silicon carbide coating over the conventional TRISO coatings. The use of such microfuel elements opens up the possibility of developing fuel elements capable of retaining fission products both under normal operating conditions and in design-basis and beyond-design-basis accidents. Variants of the design of rod-shaped accident-tolerant fuel (ATF) for water-cooled reactors based on micro-encapsulated fuel with silicon carbide coatings and cladding comprised of a composite of the type SiC–SiC are considered.
Unable to display preview. Download preview PDF.
- 1.Fuel Performance And Fission Product Behaviour in Gas Cooled Reactors, IAEA-TECDOC-978, IAEA, Vienna (1997).Google Scholar
- 2.High-Temperature Gas-Cooled Reactor Fuels and Materials, TECDOC-1645, IAEA, Vienna (2010).Google Scholar
- 3.Status of Minor Actinide Fuel Development, IAEA Nuclear Energy Ser. No. NF-T-4.6, IAEA, Vienna (2009).Google Scholar
- 4.I. E. Golubev, S. M. Kurbakov, and A. S. Chernikov, “Computational and experimental studies of pyrocarbon and silicon carbide barriers of HTGR microfuel,” At. Energ., 105, No. 1, 14–25 (2008).Google Scholar
- 5.A. V. Beleevskii, I. E. Golubev, N. V. Morozov, et al., Patent No. 2603018, “Microfuel nuclear reactor,” Byul. Izobret. Polezn. Modeli, No. 32 (2016).Google Scholar
- 6.A. V. Beleevskii, I. E. Golubev, N. V. Morozov, and A. A. Pertsev, Patent No. 2603020, “Method of manufacturing microfuel for a nuclear reactor,” ibid. Google Scholar
- 7.Advances in High-Temperature Gas-Cooled Reactor Fuel Technology, TECDOC-1674, IAEA, Vienna (2012).Google Scholar
- 9.E. I. Grishanin, G. V. Momot, G. A. Filippov, et al., “Investigation of the corrosion resistance of microfuel cladding made of silicon carbide and PyC for the operating conditions of light-water reactors in nuclear power plants,” At. Energ., 101, No. 4, 270–278 (2006).Google Scholar
- 10.V. M. Trubachev, G. A. Filippov, L. N. Falkovskii, et al., “Experimental study of the performance of microfuel protective shells for severe accident conditions in light-water reactors,” At. Energ., 103, No. 5, 302–309 (2007).Google Scholar
- 11.G. A. Filippov, E. I. Grishanin, V. M. Trubachev, et al., “Investigation of the corrosion resistance and damageability (integrity) of the microfuel cladding made of silicon carbide and pyrocarbon in a supercritical pressure water coolant,” Vopr. At. Nauki Tekh. Ser. Obesp. Bezopas. AES, No. 30, 111–121 (2011).Google Scholar
- 12.E. I. Grishanin and N. E. Kukharkin, “Microfuel innovation,” Zh. Rosenergoat., No. 9, 30–36 (2009).Google Scholar
- 13.F. Makarov, A. Ponomarenko, R. Zakharov, et al., “Creation of cladding tubes for fuel elements from composite materials based on silicon carbide,” Nanoindustriya, No. 3, 60–67 (2017).Google Scholar
- 14.Fully Ceramic Microencapsulated (FCM) Replacement Fuel for LWRs, ORNL/TM-2013/173 KAERI/TR5136/2013.Google Scholar