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Radiation damage in helium ion-irradiated reduced activation ferritic/martensitic steel

  • Xia, L.D. (Key Laboratory of Advanced Materials of Ministry of Education, School of Materials Science and Engineering, Tsinghua University) ;
  • Liu, W.B. (Key Laboratory of Advanced Materials of Ministry of Education, School of Materials Science and Engineering, Tsinghua University) ;
  • Liu, H.P. (Institute of Modern Physics, Chinese Academy of Sciences) ;
  • Zhang, J.H. (Department of Nuclear Science and Technology, Xi'an Jiaotong University) ;
  • Chen, H. (Key Laboratory of Advanced Materials of Ministry of Education, School of Materials Science and Engineering, Tsinghua University) ;
  • Yang, Z.G. (Key Laboratory of Advanced Materials of Ministry of Education, School of Materials Science and Engineering, Tsinghua University) ;
  • Zhang, C. (Key Laboratory of Advanced Materials of Ministry of Education, School of Materials Science and Engineering, Tsinghua University)
  • Received : 2017.05.23
  • Accepted : 2017.10.27
  • Published : 2018.02.25

Abstract

Nanocrystalline reduced activation ferritic/martensitic (RAFM) steel samples were prepared using surface mechanical attrition treatment (SMAT). Un-SMATed and SMATed reduced activation ferritic/martensitic samples were irradiated by helium ions at $200^{\circ}C$ and $350^{\circ}C$ with 2 dpa and 8 dpa, respectively, to investigate the effects of grain boundaries (GBs) and temperature on the formation of He bubbles during irradiation. Experimental results show that He bubbles are preferentially trapped at GBs in all the irradiated samples. Bubble denuded zones are clearly observed near the GBs at $350^{\circ}C$, whereas the bubble denuded zones are not obvious in the samples irradiated at $200^{\circ}C$. The average bubble size increases and the bubble density decreases with an increasing irradiation temperature from $200^{\circ}C$ to $350^{\circ}C$. Both the average size and density of the bubbles increase with an increasing irradiation dose from 2 dpa to 8 dpa. Bubbles with smaller size and lower density were observed in the SMATed samples but not in the un-SMATed samples irradiated in the same conditions, which indicate that GBs play an important role during irradiation, and sink strength increases as grain size decreases.

Keywords

References

  1. S.J. Zinkle, P.J. Maziasz, R.E. Stoller, Dose dependence of the microstructural evolution in neutron-irradiated austenitic stainless steel, J. Nucl. Mater. 206 (1993) 266-286. https://doi.org/10.1016/0022-3115(93)90128-L
  2. C. Xu, L. Zhang, W. Qian, J. Mei, X. Liu, The studies of irradiation hardening of stainless steel reactor internals under proton and xenon irradiation, Nucl. Eng. Technol. 48 (2016) 758-764. https://doi.org/10.1016/j.net.2016.01.007
  3. W. Wang, S. Liu, G. Xu, B. Zhang, Q. Huang, Effect of thermal aging on microstructure and mechanical properties of China low-activation martensitic steel at $550^{\circ}C$, Nucl. Eng. Technol. 48 (2016) 518-524. https://doi.org/10.1016/j.net.2015.11.004
  4. P.B. Zhang, C. Zhang, R.H. Li, J.J. Zhao, He-induced vacancy formation in bcc Fe solid from first-principles simulation, J. Nucl. Mater. 444 (2014) 147-152. https://doi.org/10.1016/j.jnucmat.2013.09.048
  5. H. Ullmaier, The influence of helium on the bulk properties of fusion reactor structural materials, Nucl. Fusion 24 (1984) 1039-1083. https://doi.org/10.1088/0029-5515/24/8/009
  6. S.J. Zinkle, B.N. Singh, Analysis of displacement damage and defect production under cascade damage conditions, J. Nucl. Mater. 199 (1992) 173-191.
  7. C.C. Wang, C. Zhang, Z.G. Yang, J.J. Zhao, Multiscale simulation of yield strength in reduced-activation ferritic/martensitic steel, Nucl. Eng. Technol. 49 (2017) 569-575. https://doi.org/10.1016/j.net.2016.10.006
  8. R.H. Li, P.B. Zhang, X.J. Li, J.H. Ding, Y.Y. Wang, J.J. Zhao, L. Vitos, Effects of Cr and W additions on the stability and migration of He in bcc Fe: a firstprinciples study, Comput. Mater. Sci. 123 (2016) 85-92. https://doi.org/10.1016/j.commatsci.2016.06.019
  9. N. Hashimoto, T.S. Byun, K. Farrell, S.J. Zinkle, Deformation microstructure of neutron-irradiated pure polycrystalline metals, J. Nucl. Mater. 1309 (2004) 947-952.
  10. F.A. Garner, M.B. Toloczko, B.H. Sencer, Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure, J. Nucl. Mater. 276 (2000) 123-142. https://doi.org/10.1016/S0022-3115(99)00225-1
  11. W.B. Liu, Y.Z. Ji, P.K. Tan, C. Zhang, C.H. He, Z.G. Yang, Microstructure evolution during helium irradiation and post-irradiation annealing in a nanostructured reduced activation steel, J. Nucl. Mater. 479 (2016) 1303-1330.
  12. H. Trinkaus, B.N. Singh, Helium accumulation in metals during irradiation e where do we stand? J. Nucl. Mater. 1303 (2003) 229-242.
  13. J. Henry, M.H. Mathon, P. Jung, Microstructural analysis of 9% Cr martensitic steels containing 0.5 at.% helium, J. Nucl. Mater. 318 (2003) 249-259. https://doi.org/10.1016/S0022-3115(03)00118-1
  14. Z. Jiao, N. Ham, G.S. Was, Microstructure of helium-implanted and protonirradiated T91 ferritic/martensitic steel, J. Nucl. Mater. 367 (2007) 440-445.
  15. Y. Sekio, S. Yamashita, N. Sakaguchi, H. Takahashi, Void denuded zone formation for Fee15Cre15Ni steel and PNC316 stainless steel under neutron and electron irradiations, J. Nucl. Mater. 458 (2015) 355-360. https://doi.org/10.1016/j.jnucmat.2014.12.054
  16. B. Mazumder, M.E. Bannister, F.W. Meyer, M.K. Miller, C.M. Parish, P.D. Edmondson, Helium trapping in carbide precipitates in a tempered F82H ferriticemartensitic steel, Nucl. Mater. Energy 1 (2015) 8-12. https://doi.org/10.1016/j.nme.2014.11.001
  17. B.N. Singh, Effect of grain size on void formation during high-energy electron irradiation of austenitic stainless steel, Philos. Mag. 29 (1974) 25-42. https://doi.org/10.1080/14786437408213551
  18. B.N. Singh, A. Foreman, Calculated grain size-dependent vacancy supersaturation and its effect on void formation, Philos. Mag. 29 (1974) 847-857. https://doi.org/10.1080/14786437408222075
  19. R. Bullough, M.R. Hayns, M.H. Wood, Sink strengths for thin film surfaces and grain boundaries, J. Nucl. Mater. 90 (1980) 44-59. https://doi.org/10.1016/0022-3115(80)90244-5
  20. K.Y. Yu, Y. Liu, C. Sun, H. Wang, L. Shao, E.G. Fu, X. Zhang, Radiation damage in helium ion irradiated nanocrystalline Fe, J. Nucl. Mater. 425 (2012) 140-146. https://doi.org/10.1016/j.jnucmat.2011.10.052
  21. N.R. Tao, Z.B. Wang, W.P. Tong, M.L. Sui, J. Lu, K. Lu, An investigation of surface nanocrystallization mechanism in Fe induced by surface mechanical attrition treatment, Acta Mater. 50 (2002) 4603-4616. https://doi.org/10.1016/S1359-6454(02)00310-5
  22. R.E. Stoller, M.B. Toloczko, et al., On the use of SRIM for computing radiation damage exposure, Nucl. Instr. Meth. Phys. Res., Sect. B. 310 (2013) 75-80. https://doi.org/10.1016/j.nimb.2013.05.008
  23. Y. Matsukawa, S.J. Zinkle, Dynamic observation of the collapse process of a stacking fault tetrahedron by moving dislocations, J. Nucl. Mater. 1309 (2004) 919-923.
  24. M.J. Caturla, N. Soneda, E. Alonso, B.D. Wirth, T.D. De La Rubia, J.M. Perlado, Comparative study of radiation damage accumulation in Cu and Fe, J. Nucl. Mater. 276 (2000) 13-21. https://doi.org/10.1016/S0022-3115(99)00220-2
  25. E.G. Fu, A. Misra, H. Wang, L. Shao, X. Zhang, Interface enabled defects reduction in helium ion irradiated Cu/V nanolayers, J. Nucl. Mater. 407 (2010) 178-188. https://doi.org/10.1016/j.jnucmat.2010.10.011
  26. H. Trinkaus, Modeling of helium effects in metals: high temperature embrittlement, J. Nucl. Mater. 133 (1985) 105-112.
  27. B.N. Singh, T. Leffers, M. Victoria, W.V. Green, Relation between mechanicalproperties and microstructure under fusion irradiation conditions, Rad. Eff. 101 (1987) 91-107. https://doi.org/10.1080/00337578708224738
  28. C. Dethloff, E. Gaganidze, V.V. Svetukhin, J. Aktaa, Modeling of helium bubble nucleation and growth in neutron irradiated boron doped RAFM steels, J. Nucl. Mater. 426 (2012) 287-297. https://doi.org/10.1016/j.jnucmat.2011.12.025
  29. J.H. Evans, An interbubble fracture mechanism of blister formation on heliumirradiated metals, J. Nucl. Mater 68 (1977) 129-140. https://doi.org/10.1016/0022-3115(77)90232-X

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