TEM Characterization of Self-ion Irradiation Damage in Nickel-base Alloy C-276 at Elevated Temperature

材料科学技术（英）, 2012, 28(11): 1039-1045.

TEM Characterization of Self-ion Irradiation Damage in Nickel-base Alloy C-276 at Elevated Temperature

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1.Key Laboratory of Artificial Micro- andVNano-structures of Ministry of Education and School of Physics and Tech-nology, Wuhan University, Wuhan 430072, Cl~ina

2.Key Laboratory of Artificial Micro- andVNano-structures of Ministry of Education and School of Physics and Tech-nology, Wuhan University, Wuhan 430072, Cl~ina

3.Key Laboratory of Artificial Micro- andVNano-structures of Ministry of Education and School of Physics and Tech-nology, Wuhan University, Wuhan 430072, Cl~ina

4.Nuclear Power Institute of China, Chengdu 610041, China

5.Suzhou Nuclear Power Research Institute, Suzhou 215004, China

关键词：镍基合金 , 辐照损伤 , TEM表征 , 离子 , C-276合金 , 透射电子显微镜 , 高温 , 峰值位移

TEM Characterization of Self-ion Irradiation Damage in Nickel-base Alloy C-276 at Elevated Temperature

Keywords： Irradiation damage , Transmission electron microscopy (TEM) , Nickel-base alloyC-276 , Super-critical water reactors ,

The microstructure of nickel-base alloy C-276 irradiated at 500 ℃ with 300 keY self-ions (Ni^+) to a peak displacement damage of 4.5 displacements per atom was investigated by transmission electron microscopy. Both black spots and dislocation loops were observed. The black spots were identified as small dislocation loops, with a density of (8.2±0.2)x10^15 cm^-3 and the average loop size of about 15 nm. An increase of dislocation loop density would lead to the increase of the hardness in C-276 alloy, and the increment in yield strength was estimated by the dispersed barrier-hardening model. In [110] orientation, Burgers vectors of the dislocation loops were determined, and it was found that they were predominantly (a/2)〈110〉. In contrast to other nickel-base alloys, no voids were observed in C-276 alloy after being irradiated at elevated temperatures.

参考文献

[1]	Z. Lu;R.G. Faulkner;G. Was .Irradiation-induced grain boundary chromium microchemistry in high alloy ferritic steels[J].Scripta materialia,2008(10):878-881.
[2]	X.Q. Li,J.J. Zhao,J.C. Xu,X. Liu.Mechanical Properties and Defective Effects of 316LN Stainless Steel by First-Principles Simulations[J].材料科学技术学报：英文版,2011(11):1029-1033.
[3]	K. Ono;M. Miyamoto;K. Arakawa;R.C. Birtcher .Dynamical response of helium bubble motion to irradiation with high-energy self-ions in aluminum at high temperature[J].Philosophical magazine: structure and properties of condensed matter,2009(6):513-524.
[4]	K. Ono;K. Arakawa;R.C. Birtcher .Intermittent rapid motion of helium bubbles in Cu during irradiation with high energy self-ions[J].Nuclear Instruments and Methods in Physics Research, Section B. Beam Interactions with Materials and Atoms,2003(0):114-117.
[5]	C. Pokor;X. Averty;Y. Brechet;P. Dubuisson;J. P. Massoud .Effect of irradiation defects on the work hardening behavior[J].Scripta materialia,2004(5):597-600.
[6]	S.X. Jin;L.P. Guo;Z. Yang .Microstructural evolution of P92 ferritic/martensitic steel under argon ion irradiation[J].Materials Characterization,2011(1):136-142.

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TEM Characterization of Self-ion Irradiation Damage in Nickel-base Alloy C-276 at Elevated Temperature

TEM Characterization of Self-ion Irradiation Damage in Nickel-base Alloy C-276 at Elevated Temperature

参考文献