Generate QR code
Open Access
Subscription Access
Evaluation of resistance to corrosion cracking of irradiated austenitic chromium-nickel steels by impact bending tests on miniature specimens
https://doi.org/10.22349/1994-6716-2020-102-2-200-215
Abstract
In this work, we present results of a bending test of miniature specimens made of chromium-nickel stainless austenitic steels of grades 321 (08Kh18N10T), 316 (06Kh16N11M3) and 304 (02Kh18N9) irradiated to various damage doses from 4 to 125 dpa in different energy neutron spectra. Effects of the damage dose and the neutron energy spectrum on the intergranular fracture energy, which determines the strength of grain boundaries, are studied. Two neutron spectra are considered: one characteristic of the active zone of PWR and WWER reactors, and the other is typical for the active zone of fast core reactors. The relationship between the resistance to corrosion cracking of irradiated chromium-nickel steels 321, 316 and 304 and the strength of grain boundaries is considered.
Keywords
austenitic chromium-nickel steels,
stress corrosion cracking,
miniature specimens,
impact bending tests
Supporting agencies: This work was carried out within the framework of collaboration with the Material Ageing Institute under the project “Vessel Internal Project VIP 1” (project “Pressure Vessel Internal”).
About the Authors
B. Z. Margolin
NRC “Kurchatov Institute” – CRISM “Prometey”
Russian Federation
Russian Federation
Dr Sc. (Eng)
49 Shpalernaya St, 191015 St Petersburg
N. E. Pirogova
NRC “Kurchatov Institute” – CRISM “Prometey”
Russian Federation
49 Shpalernaya St, 191015 St Petersburg
Russian Federation
49 Shpalernaya St, 191015 St Petersburg
A. A. Sorokin
NRC “Kurchatov Institute” – CRISM “Prometey”
Russian Federation
Russian Federation
Cand Sc. (Eng)
49 Shpalernaya St, 191015 St Petersburg
A. M. Morozov
NRC “Kurchatov Institute” – CRISM “Prometey”
Russian Federation
Russian Federation
Cand Sc. (Eng)
49 Shpalernaya St, 191015 St Petersburg
References
1. Margolin, B.Z., Sorokin, A.A. Pirogova, N.E., et al., Analysis of mechanisms inducing corrosion cracking of irradiated austenitic steels and development of a model for prediction of crack initiation, Engineering Failure Analysis, 2020, V. 107 (104235), pp. 1–20.
2. Fukuya, K., Nishioka, H., Fujii, K., Fracture behavior of austenitic stainless steels irradiated in PWR, J. Nucl. Mater, 2008, V. 378, pp. 211–219.
3. Sorokin, A.A., Margolin, B.Z., Kursevich, I.P., et al., Effect of neutron irradiation on tensile properties of materials for pressure vessel internals of WWER type reactors, J. Nucl. Mater, 2014, V. 444, pp. 373–384.
4. Miura, T., Fujii, K., Fukuya, K., Micro-mechanical investigation for effects of helium on grain boundary fracture of austenitic stainless steel, J. Nucl. Mater, 2015, V. 457, pp. 279–290.
5. Fujimoto, K., Yonezawa, T., Wachi, E., et al., Effect of the Accelerated Irradiation and Hydrogen/Helium Gas on IASCC Characteristics for Highly Irradiated Austenitic Stainless Steels, Proc. 12th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, PA, 2005, pp. 299–310.
6. Boothby, R.M., Radiation effects in nickel-based alloys, Comprehensive Nucl. Mater, 2012, V. 4, pp. 123–150.
7. Judge, C.D., Gauquelin, N., Walters, L., et al., Intergranular fracture in irradiated Inconel X-750 containing very high concentrations of helium and hydrogen, J. Nucl. Mater, 2015, V. 457, pp. 165– 172.
8. Stoller, R.E., Maziasz, P.J., Rowcliffe, A.F., Tanaka, M.P., Swelling behavior of austenitic stainless steels in a spectrally tailored reactor experiment: Implications for near-term fusion machines, J. Nucl. Mater, 1988, V. 155–157, pp. 1328–1334.
9. Brayent, K.L., Benerdzhi, S.K., et al., Okhrupchivanie konstruktsionnykh staley i splavov [Embrittlement of structural steels and alloys], Moscow: Metallurgiya, 1988.
10. Gusev, M.N., Maksimkin, O.P., 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, V. 403, pp. 121–125.
11. Trinkaus, H., Ullmaier, H., High temperature embrittlement of metals due to helium: is the lifetime dominated by cavity growth or crack growth?, J. Nucl. Mater, 1994, V. 212–215, Part 1, pp. 303–309.
12. Scott, P.A., review of irradiation assisted stress corrosion cracking, J. Nucl. Mater, 1994, V. 211, pp. 101–122.
13. Margolin, B.Z., Sorokin, A.A., Smirnov, V.I., et al., Physical and mechanical modelling of neutron irradiation effect on ductile fracture. Part 1. Prediction of fracture strain and fracture toughness of austenitic steels, J. Nucl. Mater, 2014, V. 452, pp. 595–606.
Review
For citations:
Margolin B.Z., Pirogova N.E., Sorokin A.A., Morozov A.M. Evaluation of resistance to corrosion cracking of irradiated austenitic chromium-nickel steels by impact bending tests on miniature specimens. Voprosy Materialovedeniya. 2020;(2(102)):200-215. (In Russ.) https://doi.org/10.22349/1994-6716-2020-102-2-200-215
Views:
247
Email this article 