Abstract
By the beginning of work in the 1960s, information on the properties and manufacturing technology of materials for the NRE core (based on zirconium, niobium, uranium carbides, and zirconium hydride) was absent or inconsistent. It was known that unlike mono compound of uranium with a low melting point (2,500 K), a fuel based on solid solutions of UC–ZrC and UC–NbC carbides with nearly stochastic composition can provide the heating of hydrogen up to 3,000 K. Therefore, investigations of solid solutions of uranium monocarbide with isomorphous, highly refractory zirconium, niobium, and monocarbides providing high melting points and compatibility of HREs with heat carriers became the most important material technology direction. The prospects of the development of UC–ZrC–ZrN fuel were also outlined. The manufacturing technology of these refractory materials was based on powder metallurgy methods.
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
References
Jackson, H. F., & Le, W. E. (2012). Properties and characteristics of ZrC (pp. 339–372). Amsterdam: Elsiver.
Andrievsky, R. A., Spivak, I. I. (1989). Strength of refractory compounds; Directory (p. 367). Chelyabinsk: Metallurgy.
Andrievsky, R. A., Lanin, A. G., & Rymashevsky, G. A. (1974). Strength of refractory compounds-M: Metallurgy, p. 232.
Daragan, I. D., D’jakov, E. K., Fedik I. I. et al. (2003). Fuel element assemblages of the space nuclear power propulsion systems. Moscow: Nuclear Technology Engineering Industry. vol. IV-25, under Adamov’s edition. Engineering industry, book 2.
Nuclear Technology Engineering Industry (2003). Moscow, vol. IV-25, under Adamovs’s edition. Engineering industry., book 1. 953 p. book 2. 943 p.
Lanin, A. G., & Fedik., I. I. (2008). Thermal stress resistance of materials (p. 239). Heidelberg: Springer.
RIPRA “Luch”. (2004). Affairs and people. Podolsk. RIPRA "LUCH". Ed. Fedik I.I. Podolsk, 455 p.
Andrievsky, R. A., & Umanskiy, Y. S. (1977). Interstitial phases M. Science, p. 238.
Lanin, A. G., Zubarev, P. V., & Vlasov, K. P. (1993). Research of mechanical and heat-physical properties of fuel and constructive materials of NRER. Atomic Energy, 74(1), 42–47.
Lanin, A. G., & Babajants, G. I. (2003). Structural materials of an active zone of NRER. In Engineering nuclear industry (vol. IV-25). under E.O.Adam’s edition. Moscow: Engineering Industry. book 1.
Kosycheva, L. I., Lanin, A. G., Manjuhin, V. P. et al. (1978). Research of physical-mechanical properties of fuel compositions ZrC-UC. ZrC-NbC-UC. ZrC-UC-C (vol. 111803, pp. 47–67). Podolsk: Scientific Research Institute NPO “LUCH”.
Andrievsky R. A. (1991). Powder materials technology (p. 207). Moscow: M. Metallurgija.
Andrievsky, R. A., Hromonozhkin, V. V., et al. (1969). Evaporation of uranium carbide. uranium nitride and uranium carbide-nitride. Atomic Energy, 26, 494–497.
Lanin, A. G. (1998). Strength and thermal stress resistance of structural ceramic (111 p.). Moscow: M. Moscow State Engineer Physical institute.
Nezhevenko, L. B., Groshev V. I., & Bokov, I. V. (1970). Influence of ZrC powders on properties of sintering samples. In “Refractory Carbides” (pp. 58–61). K. Naukova Dumka.
Bulychyov, V. P., Andrievsky, R. A., & Nezhevenko, L. B. (1977). Sintering of zirconium carbide. Powder Metallurgy, 1(4), 38–42.
Gerasimov, P. V., Egorov, V. S., Lanin, A. G., Nezhevenko, L. B., & Sokolov, V. A. (1982). Strength of compositions on the basis of zirconium carbide with disperse carbon inclusions. Powder Metallurgy, 11, 67–74.
Lanin, A. G., Popov, V. I., Maskaev, A., et al. (1981). Strength of carbide-graphite compositions at power and thermal loading. Problems of Strength, 112, 89–95.
Lanin, A. G., Marchev, E. V., & Pritchin, S. A. (1991). Non-isothermal sintering parameters and their influence on the structure and properties of zirconium carbide. Ceramics International, 17, 301–307.
Lanin, A. G. (2007). Physical processes microindentation of carbide monocrystals of transition metals. Functional Materials, 1(110), 383–389.
Lanin, A. G. (2004). Strength and thermo-mechanical reinforcement of the refractory ceramic materials. Izvestia of the Russian Academy of Sciences. Series Physical, 68(110), 1503–1509.
Zubarev, P. V. (1985). Heat resistance of interstitial phases (101 p.). Moscow: M. Metallurgija.
Derjavko, I. I., Egorov, V. S., Lanin, A. G., et al. (2001). Radiographic research of the residual Stresses in the rod carbide fuel elements. The Bulletin of the National Nuclear Centre of Republic Kazakhstan, 14, 95.
Fedik, I. I. Kolesov, V. S., & Mihajlov, V. N. (1985). Temperature fields and thermal stresses in nuclear-reactors (280 p.). Moscow: M. Energoatomizdat.
Lanin, A. G., Erin, O. N., & Turchin V. N. (1990). Zirconium carbide strength and plasticity. Refractory Metals and Hard Metals, 92(3), 120–124; 139–141.
Zubarev, P. V., Kuraev, A. B., Lanin, A. G., et al. (1992). Influence of a grain size on creep of zirconium carbide. FMM, 16, 122–125.
Lanin, A. G. (1995). Thermal stress resistance of porous Si\(_{3}\)N\(_{4}\). ZrC heterogeneous carbides and hydrides. Proceedings of 6th International Symposium on Fracture Mechanics of Ceramic, July 18–20, Karlsruhe, Germany.
Lanin, A. G., & Egorov, V. S. (1999). Elastic–plastic fracture of the bodies under combined influence of the thermal and mechanical loads. FCHOM, 2, 78–81.
Vlasov, N. M., & Fedik, I. I. (2001). Fuel elements of nuclear rocket engines (p. 207). Moscow: Tsniatominform.
Zelenskij, D. I., Pivovarov, O. C., Tuhvatulin, S. T. et al. (1999). Experience generalization of reactor working off of the rod carbide fuels on a complex stand “Baikal-1” and the development of applied production engineering (pp. 49–60). The Fifth International Conference “Nuclear Power Space”, Podolsk.
Katz, S. M. (1981). High-temperature heat insulating materials (p. 232). Moscow: M. Metallurgy.
Vjatkin, S. E., & Deev, A. N. (1967). Nuclear graphite (279 p.). Moscow: Atomizdat.
Kats, S. M., Gorin, A. I., & Semenov, M. V. (1972). Poroshkovaja Metallurgija, 7, 87–92.
Babajants, G. I., Golomazov, V. M., Granov, V. I., & Shmakov, V. A. (1974). Copyright certificate N 424658 “Opening. inventions. commercial machines. Trade marks”, vol. 15, p. 38.
Ponomarev-Stepnoy, N. N. (1993). Creation history of NRER in the USSR (pp. 3–18). Third Branch Conferences “Nuclear Power in Space”.
Andrievsky, R. A. (1986). Material science of hydrides (p. 129). Moscow: M Metallurgy.
Lanin, A. G., Zalivin, I. M., & Turchin, V. N. (1984). Mechanical property of hydride alloys Zr. Y. Ti. Problem of Strength, 6, 83–86.
Zubarev, P. V., & Ryzhov, P. (1979). Creep of Zr and Y hydrides inorganic materials. 16(2), 247–250.
Lanin, A. G. (2011). Influence of residual stresses on ceramic materials strength and fracture. Deformation and Fracture, 4.
Koch, C. C., Ovud’ko, I. A., Seal, S., & Veprek, S. (2007). Structural nanocrystalline materials: Fundamental and application (p. 364). Cambridge: Cambridge University Press.
Andrievsky, R. A. (2012). The basis of nanostructural materialscience: Possibilities and problems (p. 251). Moscow: Publishing house BINOM.
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
Copyright information
© 2013 Springer-Verlag Berlin Heidelberg
About this chapter
Cite this chapter
Lanin, A. (2013). Materials of the Reactor Core. In: Nuclear Rocket Engine Reactor. Springer Series in Materials Science, vol 170. Springer, Berlin, Heidelberg. https://doi.org/10.1007/978-3-642-32430-7_4
Download citation
DOI: https://doi.org/10.1007/978-3-642-32430-7_4
Published:
Publisher Name: Springer, Berlin, Heidelberg
Print ISBN: 978-3-642-32429-1
Online ISBN: 978-3-642-32430-7
eBook Packages: Physics and AstronomyPhysics and Astronomy (R0)