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Construction of Theoretical Curves of the Long-Term Strength for Neutron-Irradiated Austenitic Steels Kh18N9 and 08Kh16N11M3

  • STRUCTURAL AND TECHNOLOGICAL STRENGTH AND EFFICIENCY OF MATERIALS
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Inorganic Materials: Applied Research Aims and scope

Abstract—Having analyzed experimental data on the long-term strength of unirradiated austenitic materials and predictive dependences obtained in the context of a physical and mechanical model of intergranular fracture, the authors have determined the assurance factor for plotting the long-term strength curves for unirradiated and irradiated materials. The above model, as well as experimental results, has made it possible to calculate the normative curves for the initial and irradiated steels Kh18N9 and 08Kh16N11M3. Their validity has been verified on the basis of external and intrareactor tests.

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REFERENCES

  1. PNAE G-7-002–86. Normy rascheta na prochnost’ oborudovaniya i truboprovodov atomnykh energeticheskikh ustanovok (PNAE G-7-002–86. Standards for Calculation of the Strength of Equipment and Pipelines of Nuclear Power Plants), Moscow: Energoatomizdat, 1989.

  2. Margolin, B.Z., Gulenko, A.G., Kursevich, I.P., and Buchatsky, A.A., Forecasting the long-term strength of austenitic materials under neutron irradiation, Vopr. Materialoved., 2005, no. 2 (42), pp. 163–186.

  3. Margolin, B.Z., Gulenko, A.G., Kursevich, I.P., and Buchatskii, A.A., Modeling for fracture in materials under long-term static creep loading and neutron irradiation. Part 1. A physico-mechanical model, Strength Mater., 2006, vol. 38, no. 3, pp. 221–233.

    Article  CAS  Google Scholar 

  4. Margolin, B.Z., Gulenko, A.G., Kursevich, I.P., and Buchatskii, A.A., Modeling for fracture in materials under long-term static creep loading and neutron irradiation. Part 2. Prediction of creep rupture strength for austenitic materials, Strength Mater., 2006, vol. 3838, no. 5, pp. 449–457.

    Article  CAS  Google Scholar 

  5. Gulenko, A.G., Buchatsky, A.A., Margolin, B.Z., Kashtanov, A.D., and Fedorova, V.A., The growth rate of a crack in austenitic steels during a long static loading under creep conditions, Vopr. Materialoved., 2012, no. 2 (70), pp. 120–137.

  6. Kursevich, I.P., Margolin, B.Z., Prokoshev, O.Yu., and Kokhonov, V.I., Mechanical properties of austenitic steels under neutron irradiation: the influence of various factors, Vopr. Materialoved., 2006, no. 4 (48), pp. 55–68.

  7. Data Sheets on the Elevated Temperature Properties of 18Cr–8Ni Stainless Steel for Boiler and Heat Exchanger Seamless Tubes (SUS 304H TB)/NRIM Creep Data Sheets No. 4B, Tokyo: Natl. Res. Inst. Met., 1986.

  8. Data Sheets on the Elevated Temperature Properties of 18Cr–12Ni–Mo Stainless Steel Tubes for Boiler and Heat Exchangers (SUS 316H TB)/NRIM Creep Data Sheets No. 6B, Tokyo: Natl. Res. Inst. Met., 2000.

  9. Code Case N-47-32, Class 1, Components in Elevated Temperature Service, in Cases of Boiler and Pressure Vessel Code, New York: Am. Soc. Mech. Eng., 1976.

    Google Scholar 

  10. Stepnov, M.N., Statisticheskaya obrabotka rezul’tatov mekhanicheskikh ispytanii (Statistical Processing of the Results of Mechanical Tests), Moscow: Mashinostroenie, 1972.

  11. 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.

    Article  Google Scholar 

  12. Grishmanovskaya, R.N., Kudryavtsev, A.S., and Markov, V.G., The change in the properties of steels of grades Kh18N9 and Kh16N11M3 after operation for 130 000 hours as part of a industrial a RU BN-600reheater, Trudy 9-oi mezhdunarodnoi konferentsii “Problemy materialovedeniya pri proektirovanii, izgotovlenii i ekspluatatsii oborudovaniya AES,” 6–8 iyunya 2006 g. (Proc. 9th Int. Conf. “Problems Material Science in Design, Production, and Operation of Equipment of NPP,” June 6–8, 2006), St. Petersburg, 2006, vol. 2, pp. 290–298.

  13. Votinov, S.N., Gorynin, I.V., Nikolaev, V.A., Prokhorov, V.I., and Razov, I.A., Influence of neutron irradiation on the long-term strength of austenitic stainless steels, Trudy nauchno-tekhnicheskoi konferentsii “Atomnaya energetika, toplivnye tsikly, radiatsionnoe materialovedenie,” Ul’yanovsk, 5–10 oktyabrya 1970 (Proc. Sci.-Tech. Conf. “Nuclear Energetics, Fuel cycles, and Radiation Material Science,” Ulyanovsk, October 5–10, 1970), Moscow: Sov. Ekon. Vzaimopomoshchi, 1971, vol. 3, pp. 612–630.

  14. Kursevich, I.P., Lapin, A.N., and Nikolaev, V.A., Radiation damage of structural materials used in reactors of the BN type, in Radiatsionnye effekty izmenenii mekhanicheskikh svoistv konstruktsionnykh materialov i metody ikh issledovanii (Radiation Effects of Change of Mechanical Properties of Constructional Materials and Their Study Methods), Kiev: Naukova Dumka, 1976.

  15. Andreev, V.V., Nikolaev, V.A., and Parshin, A.M., Radiation damage of steels during irradiation in a fast reactor, in Radiatsionnye effekty izmenenii mekhanicheskikh svoistv konstruktsionnykh materialov i metody ikh issledovanii (Radiation Effects of Change of Mechanical Properties of Constructional Materials and Their Study Methods), Kiev: Naukova Dumka, 1976.

  16. Votinov, S.N., Prokhorov, V.I., and Ostrovskii, Z.E., Obluchennye nerzhaveyushchie stali (Irradiated Stainless Steels), Moscow: Nauka, 1987.

  17. Votinov, S.N., Prokhorov, V.I., and Fin’ko, A.G., Changes in the characteristics of heat-resistant pipes from 1Kh18N10T steel at 550–700°C during irradiation, Preprint of the Research Inst. of Atomic Reactors, Dmitrovgrad, 1980, no. NIIAR-39 (447).

  18. Votinov, S.N., Losev, N.P., Prokhorov, V.I., Samsonov, B.V., Tsykanov, V.A., and Fin’ko, A.G., Rating the long-term strength of constructional materials inside a reactor, Strength Mater., 1971, vol. 3, no. 5, pp. 558–561.

    Article  Google Scholar 

  19. Votinov, S.N., Prokhorov, V.I., and Fin’ko, A.G., Comparative estimate of the long-term strength of KhN77TYuR alloy and Kh18N10T at 700°C under in-pile irradiation conditions, Strength Mater., 1976, vol. 8, no. 12, pp. 1407–1412.

    Article  Google Scholar 

  20. Kurata, Y., Itabashi, Y., Mimura, H., Kikuchi, T., Amezawa, H., Shimakawa, S., Tsuji, H., and Shindo, M., In-pile and post-irradiation creep of type 304 stainless steel under different neutron spectra, J. Nucl. Mater., 2000, vol. 9, pp. 286–390.

    Google Scholar 

  21. Pisarenko, G.S., Pisarenko, G.S., and Kiselevskii, V.N., Prochnost’ i plastichnost’ materialov v radiatsionnykh potokakh (Strength and Plasticity of Materials in Radiation Flows), Kiev: Naukova Dumka, 1979.

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Correspondence to A. G. Gulenko.

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Translated by O. Maslova

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Gulenko, A.G., Margolin, B.Z., Buchatskii, A.A. et al. Construction of Theoretical Curves of the Long-Term Strength for Neutron-Irradiated Austenitic Steels Kh18N9 and 08Kh16N11M3. Inorg. Mater. Appl. Res. 9, 1254–1262 (2018). https://doi.org/10.1134/S2075113318060291

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