TEM Study of ODS Alloy Doped with Helium Ions and Re-irradiated with Swift Xe Ions
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DOI:
https://doi.org/10.15625/0868-3166/29/3SI/14286Keywords:
ODS alloys, helium bubbles, oxide nanoparticles, swift heavy ions (SHIs)Abstract
Oxide dispersion strengthened (ODS) alloys are considered as candidates for fuel assembly claddings, since nano-oxides, among other things, contribute to the gas swelling suppression. However, it is still unknown that how oxides will behave in this capacity under the exposure to fission fragments. Transmission electron microscopy has been applied to study helium porosity in a ferritic EP450ODS alloy doped with helium by the ion implantation and re-irradiated with high energy Xe ions, which is used for simulating fission fragments at room temperature followed by annealing. It has been shown that helium bubbles mainly decorate the structural defects and grain boundaries both in helium doped only and in re-irradiated with Xe samples. Furthermore, we have found that there was not significant changes in the size distributions of helium bubbles in ferritic matrix due to the re-irradiation with Xe. The only effect of irradiation with swift Xe ions on the alloy structure is the amorphization of dispersed oxides in it. But, as a result of amorphization of dispersed oxides, helium bubbles were detected at the oxide-matrix (O-M) interfaces as well as inside amorphous oxides, while they have not been observed inside crystalline nano-oxides and seldom connecting to the O-M interface in the He-doped only samples. That means the nano-oxides amorphized by fission fragments can promote the better helium bubbles pinning in actual operation of the fuel assembly cladding in a nuclear reactor.Downloads
References
R. S. Barnes and D. J. Mazey. The migration and coalescence of inert gas bubbles in metals. Proc. R. Soc. Lond. A275 (1963) 47-57.
H. Ullmaier. The influence of helium on the bulk properties of fusion reactor structural materials. Nuclear Fusion, Vol.24, No.8 (1984).
P. J. Goodhew and S. K. Tyler. Helium Bubble Behaviour in b.c.c. Metals Below 0.65Tm. Proceedings of the Royal Society of London. Series A, Mathematical and PhysicalSciences, Vol. 377, No. 1769 (1981) 151-184.
V.N. Chernikov, A.P. Zakharov and P.R. Kazansky. Relation between swelling and embrittlement during post-irradiation annealing and instability of helium – vacancy complexs in nickel. Journal of Nuclear Materials 155-157 (1988) 1142-l 145.
H. Schroeder. High temperature embrittlement of metals by helium, Radiation Eflects 78 (1983) 297-314.
V.M. Chernov, M.V. Leonteva-Smirnova, et al. Structural materials for fusion power reactors—the RF R&D activities. Nucl. Fusion 47 (2007) 839–848.
N. Baluc, K. Abe, et.al. Status of R&D activities on materials for fusion power reactors. Nucl. Fusion 47 (2007) S696–S717.
Luke L. Hsiung, Michael J. Fluss, Scott J. Tumey, William B. Choi1, Yves Serruys, Francois Willaime, Akihiko Kimura. Formation Mechanism and the Role of Nanoparticles in Fe-Cr ODS Steels Developed for Radiation Tolerance. Physical Review B82 (2010) 184103.
Chenyang Lu, Zheng Lu, Rui Xie, Chunming Liu, Lumin Wang. Microstructure of a 14Cr-ODS ferritic steel before and after helium ion implantation. Journal of Nuclear Materials 455 (2014) 366–370.
G.R. Odette, D.T. Hoelzer. Irradiation-tolerant nanostructured ferritic alloys: transforming helium from a liability to an asset. JOM 62 (2010) 84–92.
K. Yutani, H. Kishimoto, R. Kasada, A. Kimura. Evaluation of Helium effects on swelling behavior of oxide dispersion strengthened ferritic steels under ion irradiation. Journal of Nuclear Materials 367–370 (2007) 423–427.
Yanan Jin, Yong Jiang, Litong Yang, Guoqiang Lan, G. Robert Odette, Takuya Yamamoto, Jiacheng Shang, and Ying Dang. First principles assessment of helium trapping in Y2TiO5 in nano-featured ferritic alloys. Journal of Applied Physics 116 (2014) 143501.
V.A. Skuratov, A.S. Sohatsky, J.H. O’Connell, K. Kornieieva, A.A. Nikitina, J.H. Neethling, V.S. Ageev. Swift heavy ion tracks in Y2Ti2O7 nanoparticles in EP450 ODS steel. Journal of Nuclear Materials 456 (2015) 111–114.
V.A. Skuratov, V.V. Uglov, J. O’Connell, A.S. Sohatsky, J.H. Neethling, S.V. Rogozhkin. Radiation stability of the ODS alloys against swift heavy ion impact. Journal of Nuclear Materials 442 (2013) 449–457.
A.A. Nikitina, V.S. Ageev, A.P. Chukanov, V.V. Tsvelev, N.P. Porezanov, and O.A. Kruglov. R&D of ferritic – martensitic steel EP450 ODS for fuel pin clappings of prospective fast reactors. J. Nucl. Mater. 428 (2012) 117–124.
J.F. Ziegler, J.P. Biersack, U. Littmark. Vol. 1, Pergamon, New York, 1985. http://www.srim.org/.
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