Browse > Article
http://dx.doi.org/10.1016/j.net.2017.10.012

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)
Publication Information
Nuclear Engineering and Technology / v.50, no.1, 2018 , pp. 132-139 More about this Journal
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
Grain Boundary; Helium Bubble; Irradiation Temperature; Reduced Activation Ferritic/Martensitic Steel;
Citations & Related Records
Times Cited By KSCI : 3  (Citation Analysis)
연도 인용수 순위
1 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.   DOI
2 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.   DOI
3 H. Trinkaus, Modeling of helium effects in metals: high temperature embrittlement, J. Nucl. Mater. 133 (1985) 105-112.
4 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.   DOI
5 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.   DOI
6 J.H. Evans, An interbubble fracture mechanism of blister formation on heliumirradiated metals, J. Nucl. Mater 68 (1977) 129-140.   DOI
7 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.   DOI
8 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.   DOI
9 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.   DOI
10 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.   DOI
11 H. Ullmaier, The influence of helium on the bulk properties of fusion reactor structural materials, Nucl. Fusion 24 (1984) 1039-1083.   DOI
12 S.J. Zinkle, B.N. Singh, Analysis of displacement damage and defect production under cascade damage conditions, J. Nucl. Mater. 199 (1992) 173-191.
13 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.   DOI
14 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.   DOI
15 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.
16 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.   DOI
17 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.   DOI
18 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.
19 H. Trinkaus, B.N. Singh, Helium accumulation in metals during irradiation e where do we stand? J. Nucl. Mater. 1303 (2003) 229-242.
20 Z. Jiao, N. Ham, G.S. Was, Microstructure of helium-implanted and protonirradiated T91 ferritic/martensitic steel, J. Nucl. Mater. 367 (2007) 440-445.
21 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.   DOI
22 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.   DOI
23 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.   DOI
24 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.   DOI
25 B.N. Singh, A. Foreman, Calculated grain size-dependent vacancy supersaturation and its effect on void formation, Philos. Mag. 29 (1974) 847-857.   DOI
26 R. Bullough, M.R. Hayns, M.H. Wood, Sink strengths for thin film surfaces and grain boundaries, J. Nucl. Mater. 90 (1980) 44-59.   DOI
27 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.   DOI
28 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.   DOI
29 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.