Abstract—The results of studying the mechanisms of fracture and embrittlement of the Kh18N9 and Kh18N10T austenitic steels under long-term neutron irradiation at elevated temperatures are given. The effects of the temperature and time of irradiation and the neutron radiation dose on the fracture strain and fracture mechanisms are analyzed. On the basis of the results obtained and specially performed experiments, a synergistic mechanism of embrittlement of the material under conditions of long-term high-temperature irradiation is proposed and substantiated, which is determined by the following two factors: thermal aging and helium diffusion. The thermal aging leads to the formation of various phases at grain boundaries and, hence, to a decrease in the grain boundary strength. Helium diffusion at elevated temperatures gives rise to the accumulation and growth of helium bubbles at weakened grain boundaries.
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The leading developer of this standard for the operating entity Rosenergoatom Concern is the Central Research Institute of Structural Materials Prometey.
REFERENCES
Barnes, R.S., Embrittlement of stainless steels nickel based alloys at high temperature induced by neutron radiation, Nature, 1965, vol. 206, p. 1307.
Ward, A.L. and Holmes, J.J., Ductility loss in fast reactor irradiated stainless steel, Nucl. Appl. Technol., 1970, vol. 9, pp. 771–772.
Claudson, T.T. and Barker, R.W., The effects of fast flux irradiation on the mechanical properties and dimensional stability of stainless steel, Nucl. Appl. Technol., 1970, vol. 9, pp. 10–23.
Votinov, S.N., Prokhorov, V.I., Balashov, V.D., et al., The role of irradiation in the high-temperature embrittlement of steel, in Radiatsionnaya fizika tverdogo tela i reaktornoe materialovedenie (Radiation Physics of Solids and Reactor Material Science), Moscow: Atomizdat, 1970, pp. 82–84.
Fish, R.L. and Hunter, C.W., STP611: Tensile Properties of Fast Reactor Irradiated Type 304 Stainless Steel, West Conshohocken, Pa: ASTM Int., 1976, pp. 119–138.
Zelenskii, V.F., Kiryukhin, N.M., Neklyudov, I.M., et al., Vysokotemperaturnoe radiatsionnoe okhrupchivanie materialov. Analiticheskii obzor (High-Temperature Radiation Brittleness of Materials: Analytical Review), Kharkov: Khar’k. Fiz.-Tekh. Inst., 1983.
Votinov, S.N., Prokhorov, V.I., and Ostrovskii, Z.E., Obluchennye nerzhaveyushchie stali (Irradiated Stainless Steels), Moscow: Nauka, 1987.
Tavassoli, A.A., Picker, C., and Wareign, J., Data Collection on the Effect of Irradiation on the Mechanical Properties of Austenitic Stainless Steels and Weld Metals, West Conshohocken, PA: ASTM Int., 1997, pp. 995–1010.
Voevodin, V.N. and Neklyudov, I.M., Evolyutsiya strukturno-fazovogo sostoyaniya i radiatsionnaya stoikost’ konstruktsionnykh materialov (Evolution of Structural-Phase State and Radiation Resistance of Construction Materials), Kyiv: Naukova Dumka, 2006.
Hugon, M., Update on EURATOM R&D activities in nuclear fission and radiation protection, PERFORM60 Final Workshop, Les Renardieres, December 10–12, 2013, Brussels, 2013.
Kursevich, I.P., Margolin, B.Z., Prokoshev, O.Yu., Smirnov, V.I., Fedorova, V.A., Nesterova, E.V., and Petrov, S.N., Effect of long-term operational aging on the mechanical properties and microstructure of austenitic 18Cr-9Ni steel and the weld metal, Inorg. Mater.: Appl. Res., 2013, vol. 4, no. 6, pp. 562–574.
Margolin, B.Z., Gulenko, A.G., Buchatskii, A.A., Nesterova, E.V., and Kashtanov, A.D., Study of the effect of thermal aging on durability and plasticity of Kh18N9 steel, Inorg. Mater.: Appl. Res., 2011, vol. 2, no. 6, pp. 633–639.
Fedorova, V.A., Margolin, B.Z., Kashtanov, A.D., and Pozdnyakov, M.L., Effect of thermal aging on growth rate of fatigue crack in 10Cr18Ni9 steel and metal of welding joint, Vopr. Materialoved., 2012, no. 3 (71), pp. 126–135.
Neustroev, V.S., Belozerov, S.V., Bulanova, T.M., Varivtsev, A.V., Zhemkov, I.Yu., Karsakov, A.A., Makarov, E.I., Obukhov, A.V., and Slezko, V.S., Analysis of the bar of the actuator of the emergency control AR2 rod after operation in the BOR-60 reactor for about 32 years at high temperatures, Materialy X Rossiiskaya konferentsiya po reaktornomu materialovedeniyu (Proc. X Russ. Conf. on Reactor Material Science), Dmitrovgrad: Nauchno-Issled. Inst. At. Reakt., 2013, pp. 647–664.
Kursevich, I.P., Prokoshev, O.Yu., and Potapova, V.A., Operational damage of metal of intracase equipment of BN-600 reactor, in Radiatsionnoe materialovedenie i konstruktsionnaya prochnost’ reaktornykh materialov (Radiation Material Science and Constructional Strength of Reactor Materials), Gorynin, I.V., Ed., St. Petersburg: Tsentr. Nauchno-Issled. Inst. Kompoz. Mater. Prometei, 2002, pp. 212–221.
McClintock, P.A. and Argon, A.S., Mechanical Behavior of Materials, Reading, Ma: Addison-Wesley, 1966.
Karzov, G.P., Margolin, B.Z., and Shvetsova, V.A., Fiziko-mekhanicheskoe modelirovanie protsessov razrusheniya (Physical-Mechanical Modeling of Destruction Processes), St. Petersburg: Politekhnika, 1993.
Engel, L. and Klingele, H., An Atlas of Metal Damage: Surface Examination by Scanning Electron Microscope, St. Louis: Mosby, 1981.
Mulford, R.A., Grain-boundary embrittlement of Ni and Ni alloys, in Treatise on Materials Science and Technology, Briant, C.L. and Banerji, S.K., Eds., Amsterdam: Elsevier, 1983, vol. 25, pp. 1–19.
Zaluzhnyi, A.G., Sokurskii, Yu.N., and Tebus, V.N., Gelii v reaktornykh materialakh (Helium in Reactor Materials), Moscow: Energoatomizdat, 1988.
Neklyudov, I.M., Morozov, A.N., Zhurba, V.I., Ku-lish, V.G., and Galitskii, A.G., Capture of hydrogen isotopes in Cr18Ni10Ti steel implanted by helium ions, Vopr. At. Nauki Tekh., Ser.: Termoyad. Sint., 2008, no. 2, pp. 41–46.
Denisov, E.A., Kurdyumov, A.A., Kompaniets, T.N., et al., Hydrogen and radiogenic helium in 12Cr18Ni10Ti steel, Vopr. At. Nauki Tekh., Ser.: Termoyad. Sint., 2008, no. 2, pp. 56–66.
Holmes, J.J., Robbins, R.E., and Brimhall, J.L., Effect of fast reactor irradiation on the tensile properties of 304 stainless steel, J. Nucl. Mater., 1969, vol. 32, pp. 330–339.
Horak, J.A., Sikka, V.K., and Raske, D.T., Review of effects of long-term aging on the mechanical properties and microstructures of types 304 and 316 stainless steel, Proc. Int. Conf. on Nuclear Power Plant Aging, Availability Factor, and Reliability Analysis, San Diego, 1985, pp. 301–313.
Gusev, M.N., Maksimkin, O.P., and Garner, F.A., Peculiarities of plastic flow involving “deformation waves” observed during low-temperature tensile tests of highly irradiated 12Cr18Ni10Ti and 08Cr16Ni11Mo3 steels, J. Nucl. Mater., 2010, vol. 403, pp. 121–125.
Gusev, M.N., Field, K.G., and Busby, J.T., Strain-induced phase transformation at the surface of an AISI-304 stainless steel irradiated to 4.4 dpa and deformed to 0.8% strain, J. Nucl. Mater., 2014, vol. 446, pp. 187–192.
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Shvetsova, V.A., Prokoshev, O.Y., Margolin, B.Z. et al. Synergistic Mechanism of Radiation Embrittlement of Austenitic Stainless Steels under Long-Term High-Temperature Irradiation. Inorg. Mater. Appl. Res. 9, 1188–1197 (2018). https://doi.org/10.1134/S2075113318060230
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DOI: https://doi.org/10.1134/S2075113318060230