

Features of channel fracture for irradiated austenitic steels. Part 2. Channel fracture model and criterion
https://doi.org/10.22349/1994-6716-2025-121-1-205-224
Abstract
On the basis of experimental data considered in the first part of the paper the channel fracture model is represented and channel fracture criterion is formulated for irradiated austenitic steels. The model and criterion are based on the initiation of microcracks in channel deformation plane due to intersection with secondary channels and on the microcracks growth by shear. The proposed model and criterion of the microcracks initiation in channel deformation plane explain why channel fracture is observed in irradiated FCC metals and never observed in irradiated BCC metals although channel deformation being necessary condition for channel fracture occurs in the both metals. Procedure for the criterion parameter determination is proposed on the basis of the test results of standard tensile cylindrical specimen and cylindrical specimen with circular notch tested at one temperature over the channel fracture temperature range. Numerical values of the criterion parameters are found when using the test results represented in the first part of the paper. The proposed channel fracture criterion has been verified as applied to irradiated 18Cr–9Ni steel by comparison of the experimental and calculated values of the fracture strain for specimens with various stress triaxialities and for specimens tested at different temperatures.
About the Authors
B. Z. MargolinRussian Federation
Dr Sc. (Eng),
49 Shpalernaya St, 191015 St Petersburg
V. A. Shvetsova
Russian Federation
Cand Sc. (Phys-Math),
49 Shpalernaya St, 191015 St Petersburg
A. A. Sorokin
Russian Federation
Cand Sc. (Eng),
49 Shpalernaya St, 191015 St Petersburg
E. A. Zernov
Russian Federation
49 Shpalernaya St, 191015 St Petersburg
N. E. Pirogova
Russian Federation
Cand Sc. (Eng),
49 Shpalernaya St, 191015 St Petersburg
A. A. Buchatsky
Russian Federation
Cand Sc. (Eng),
49 Shpalernaya St, 191015 St Petersburg
References
1. Sharp, J.V., Correlation between cleared channels and surface slip steps in neutron irradiated copper crystals, Radiation Effects: Incorporating Plasma Science and Plasma Technology, 1972, V. 14, pp. 71–75.
2. Byun, T.S., Hashimoto, N., Farrell, K., Deformation mode map of irradiated 316 stainless steel in true stress-dose space, JNM, 2006, V. 351, pp. 303–315.
3. Gussev, M.N., Field, K.G., Busby, J.T., Deformation localization and dislocation channel dynamics in neutron-irradiated austenitic stainless steels, JNM, 2015, V. 460, pp. 139–152.
4. Doyle, P.J., Benensky, K.M., Zincle, S.J., Modelling of dislocation channel width evolution in irradiated metals, JNM, 2017. DOI: 10.1016/j.jnucmat.2017.10.063
5. Barrioz, P.O., Hure, J., Tanguy, B., Effect of dislocation channeling on void growth to coalescence in FCC crystals, Materials Science & Engineering: A. URL: https://doi.org/10.1016/j.msea.2019.01.115
6. Griffiths, M., Effect of neutron irradiation on the mechanical properties, swelling and creep of austenitic stainless steels, Materials, 2021, V. 14.
7. Griffiths, M., Strain localisation and fracture of nuclear reactor core materials, J. Nucl. Eng., 2023, V. 4, pp. 338–374.
8. Fish, R.L., Hunter, C.W., Tensile properties of fast reactor irradiated type 304 stainless steel. Irradiation effects on microstructure and properties of metals, ASTM STP 611, American Society for Testing and Materials, 1976, pp. 119–138.
9. Hunter, C.W., Fish, R.L., Holmes, J.J., Channel Fracture in Irradiated EBR-II Type 304 Stainless Steel, American Nuclear Society Transactions, 1972, V. 15, No 1, pp. 254–255.
10. Huang, F.H., Comparison of fracture behavior for low-swelling ferritic and austenitic alloys irradiated in the fast flux test facility (FFTF) to 180 dpa, Engineering Fracture Mechanics, 1992, V. 43, No 5, pp. 733–748.
11. Fukuya, K., Current understanding of radiation-induced degradation in light water reactor structural materials, J. Nuclear Science and Technology, 2013, V. 50, No 3, pp. 213–254.
12. Fractography, ASM Handbook, ASM International, The Materials Information Company, 1998, V. 12.
13. Rozhansky, V.N., O mekhanizme razvitiya zarodyshevykh treshchin v kristallakh pri ikh plasticheskom deformirovanii [On the mechanism of development of nucleus cracks in crystals during their plastic deformation]: Reports of the Academy of Sciences of the USSR, 1958, V. 123, No 4, pp. 648–651.
14. Ivanova, V.S., Gorodienko, L.K., Geminov, V.N., et al., Rol dislokatsy v uprochnenii i razrushenii metallov [The role of dislocations in the hardening and fracture of metals], Moscow: Nauka, 1965.
15. Foreman, A.J.E., Sharp, J.V., A mechanism for the sweeping-up of loops by glide dislocations during deformation, Phil. Mag., 1969, V. 19, pp. 931–937.
16. Si, G., Libovits, G., Matematicheskaya teoriya khrupkogo razrusheniya [Mathematical theory of brittle fracture], Razrushenie. Matematicheskie osnovy teorii razrusheniya, Moscow: Mir, 1975, V 2, pp. 84– 203.
17. Malinin, N.N., Prikladnaya teoriya plastichnosti i polzuchesti [Applied theory of plasticity and creep], Moscow: Mashinostroenie, 1975.
18. Margolin, B.Z., Shvetsova, V.A., Gulenko, A.G., Kostylev, V.I., Prometey local approach to brittle fracture: development and application, Eng. Fract. Mech., 2008, V. 75, pp. 3483–3498.
19. Chaouadi, R., Effect of irradiation-induced plastic flow localization on ductile crack resistance behavior of a 9% Cr tempered martensitic steel, JNM, 2008, V. 372, pp. 379–390.
20. Patra, A., McDowell, D.L., Continuum modelling of localized deformation in irradiated bcc materials, JNM, 2013, V. 434, pp. 414–427.
21. Margolin, B.Z., Sorokin, A.A., Buchatsky, A.A., Shvetsova, V. A . , Proko - shev, O.Yu., Pirogova, N.E., Kharakteristiki i mekhanizmy razrusheniya obluchennykh austenitnykh stalei v oblasti povyshennykh temperatur i formulirovka kriteriya razrusheniya. Ch. 1: Eksperimentalnye issledovaniya [Characteristics and mechanisms of fracture of irradiated austenitic steels in the range of elevated temperatures and formulation of the fracture criterion. Part 1: Experimental research], Voprosy Materialovedeniya, 2022, No 2 (110), pp. 185–202.
22. Bridzhmen, P., Issledovanie bolshikh plasticheskikh deformatsy i razryva [Investigation of large plastic deformations and rupture], Moscow: Izd-vo inostr. lit, 1955.
23. Chopra, O.K., Rao, A.S., A review of irradiation effects on LWR core internal materials – Neutron embrittlement, Journal of Nuclear Materials, 2011, V. 412, pp. 195–208.
24. 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, Journal of Nuclear Materials, 2014, V. 444, pp. 373–384.
25. Petrov, S.N., Prokoshev, O.Yu., Margolin, B.Z., Shumko, A.M., Carbide forming special features and fracture mechanism under the austenitic chromium-nickel 304 steel post-life ageing, Materials Phy sics and Mechanics, 2018, V. 38, No 1.
Review
For citations:
Margolin B.Z., Shvetsova V.A., Sorokin A.A., Zernov E.A., Pirogova N.E., Buchatsky A.A. Features of channel fracture for irradiated austenitic steels. Part 2. Channel fracture model and criterion. Voprosy Materialovedeniya. 2025;(1(121)):205-224. (In Russ.) https://doi.org/10.22349/1994-6716-2025-121-1-205-224