Effect of Test Temperature on Mechanical Properties of Austenitic 0.12C18Cr10NiTi and 0.08C16Cr11Ni3Mo Steels Irradiated by Fast Neutrons in the BN-350 Reactor

Abstract:

12C18Cr10NiТi and 0.08C16Cr11Ni3Мo austenitic steels serve as structural materials for fuel assembly covers in the BN-350 fast reactor, as well as for the covers of transport packagings for transportation and storage of spent nuclear fuel (SNF). To predict failure of these elements, it is of paramount importance to know their mechanical properties at elevated temperatures after in-pile irradiation. We performed tensile and creep tests at room temperature (RT), 350 °C and 450 °C of irradiated samples cut from the higher half of fuel duct pipes of the BN-350 reactor. A non-monotonic temperature dependence of tensile strength, yield stress, and relative elongation was shown. Microstructural investigation revealed the origin of this dependence lies in the different distribution of carbides and is also associated with the formation of α'-phase.

• Periodical: Defect and Diffusion Forum (Volume 375)
• Pages: 134-138
• DOI: https://doi.org/10.4028/www.scientific.net/DDF.375.134
• Online since: May 2017
• Authors: Alexey Dikov, Sergey Kislitsin, Ivan Chernov*
• Keywords: Austenitic Steels, Mechanical Properties, Microstructure, Neutron Irradiation, Thermal Creep

References

[1] K.B. Jones, R. E. Lehnert, I.D. McInnes et al., Transportation and storage cask for spent nuclear fuel, U.S. Patent 5, 406, 600. (1994).

[2] Operation and maintenance of spent fuel storage and transportation casks/containers IAEA, Vienna, Austria, 2007, p.9, http: /www-pub. iaea. org/books.

[3] B.A. Kalin, V.I. Polsky, V.L. Yakushin, I.I. Chernov, Material science problems of ecology in the field of nuclear energy: Textbook, NRNU MEPhI, Moscow, 2010 (in Russian).

[4] S.V. Ruban, O.P. Maksimkin and S.V. Rybin, Anomalous effect of the change in the magnetic and mechanical properties of irradiated stainless steel 12X18H10T during annealing 400 °C, Bulletin of the NNC of Kazakhstan Republic, 3(47) (2011).

[5] S.B. Kislitsin, A.S. Dikov, D.A. Satpayev and A.S. Larionov, Postradiation tests of structural steels - materials of covers of spent spent nuclear fuel BN-350 reactor, In: Proc. of 11th Internat. Conf. Interaction of radiation with a solids, Minsk, Belarus., 2015, pp.433-435.

[6] A.S. Dikov, I.I. Chernov and S.B. Kislitsin, Influence of the test temperature on the creep rate of the 0. 12C18Cr10NiTi structural steel irradiated in BN-350, Physics and Chemistry of Material Processing (2017) (in Press, in Russian).

DOI: 10.1134/s2075113318030127

[7] O.P. Maksimkin and O.V. Tivanova, Influence of neutron irradiation on temperature-velocity changes in the strength and plasticity characteristics of the alloy 0. 3C20Cr45Ni4MoNbBZr and steel 0. 12C18Cr10NiTi, Problems in Atomic Science and Technology. Series: Physics of Radiation Damage and Radiation Material Science 3(83) (2003).

[8] E.N. Shcherbakov, A.V. Kozlov, P.I. Yagovitin et al., Influence of damage rate on physical and mechanical properties and swelling of 18Cr–9Ni austenitic steel in the range of 3×109 to 4×108 dpa/s, J. Nucl. Mater. 386–388 (2009) 152–156.

DOI: 10.1016/j.jnucmat.2008.12.080

[9] B.A. Kalin, P.A. Platonov, Yu.V. Tuzov et al. Physical material science. Textbook for universities, V. 6, Structural materials for nuclear engineering, NRNU MEPhI, Moscow, (2012).