Standard

Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions. / Aydogan, E.; Chen, T.; Gigax, J. G.; Chen, D.; Wang, X.; Dzhumaev, P. S.; Emelyanova, O. V.; Ganchenkova, M. G.; Kalin, B. A.; Leontiva-Smirnova, M.; Valiev, R. Z.; Enikeev, N. A.; Abramova, M. M.; Wu, Y.; Lo, W. Y.; Yang, Y.; Short, M.; Maloy, S. A.; Garner, F. A.; Shao, L.

In: Journal of Nuclear Materials, Vol. 487, 15.04.2017, p. 96-104.

Research output: Contribution to journal › Article › peer-review

Harvard

Aydogan, E, Chen, T, Gigax, JG, Chen, D, Wang, X, Dzhumaev, PS, Emelyanova, OV, Ganchenkova, MG, Kalin, BA, Leontiva-Smirnova, M, Valiev, RZ, Enikeev, NA, Abramova, MM, Wu, Y, Lo, WY, Yang, Y, Short, M, Maloy, SA, Garner, FA & Shao, L 2017, 'Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions', Journal of Nuclear Materials, vol. 487, pp. 96-104. https://doi.org/10.1016/j.jnucmat.2017.02.006

APA

Aydogan, E., Chen, T., Gigax, J. G., Chen, D., Wang, X., Dzhumaev, P. S., Emelyanova, O. V., Ganchenkova, M. G., Kalin, B. A., Leontiva-Smirnova, M., Valiev, R. Z., Enikeev, N. A., Abramova, M. M., Wu, Y., Lo, W. Y., Yang, Y., Short, M., Maloy, S. A., Garner, F. A., & Shao, L. (2017). Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions. Journal of Nuclear Materials, 487, 96-104. https://doi.org/10.1016/j.jnucmat.2017.02.006

Vancouver

Aydogan E, Chen T, Gigax JG, Chen D, Wang X, Dzhumaev PS et al. Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions. Journal of Nuclear Materials. 2017 Apr 15;487:96-104. https://doi.org/10.1016/j.jnucmat.2017.02.006

Author

Aydogan, E. ; Chen, T. ; Gigax, J. G. ; Chen, D. ; Wang, X. ; Dzhumaev, P. S. ; Emelyanova, O. V. ; Ganchenkova, M. G. ; Kalin, B. A. ; Leontiva-Smirnova, M. ; Valiev, R. Z. ; Enikeev, N. A. ; Abramova, M. M. ; Wu, Y. ; Lo, W. Y. ; Yang, Y. ; Short, M. ; Maloy, S. A. ; Garner, F. A. ; Shao, L. / Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions. In: Journal of Nuclear Materials. 2017 ; Vol. 487. pp. 96-104.

BibTeX

@article{a549c602671541b8907cfc100ae405fc,
title = "Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions",
abstract = "EK-181 is a low-activation ferritic/martensitic steel that is an attractive candidate for in-core component materials for both fast reactors and fusion reactors. To assess the effect of microstructural engineering on radiation response, two variants of EK-181 were studied: one in an annealed condition and the other subject to severe plastic deformation. These specimens were irradiated with 3.5 MeV Fe self-ions up to 400 peak displacements per atom (dpa) at temperatures ranging from 400 °C to 500 °C. The deformation did not suppress swelling over the whole irradiated region. Instead, deformed samples showed higher swelling in the near-surface region. Void swelling was found to be correlated with grain boundary instability. Significant grain growth occurred when steady-state void growth started.",
author = "E. Aydogan and T. Chen and Gigax, {J. G.} and D. Chen and X. Wang and Dzhumaev, {P. S.} and Emelyanova, {O. V.} and Ganchenkova, {M. G.} and Kalin, {B. A.} and M. Leontiva-Smirnova and Valiev, {R. Z.} and Enikeev, {N. A.} and Abramova, {M. M.} and Y. Wu and Lo, {W. Y.} and Y. Yang and M. Short and Maloy, {S. A.} and Garner, {F. A.} and L. Shao",
year = "2017",
month = apr,
day = "15",
doi = "10.1016/j.jnucmat.2017.02.006",
language = "English",
volume = "487",
pages = "96--104",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier",

}

RIS

TY - JOUR

T1 - Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions

AU - Aydogan, E.

AU - Chen, T.

AU - Gigax, J. G.

AU - Chen, D.

AU - Wang, X.

AU - Dzhumaev, P. S.

AU - Emelyanova, O. V.

AU - Ganchenkova, M. G.

AU - Kalin, B. A.

AU - Leontiva-Smirnova, M.

AU - Valiev, R. Z.

AU - Enikeev, N. A.

AU - Abramova, M. M.

AU - Wu, Y.

AU - Lo, W. Y.

AU - Yang, Y.

AU - Short, M.

AU - Maloy, S. A.

AU - Garner, F. A.

AU - Shao, L.

PY - 2017/4/15

Y1 - 2017/4/15

N2 - EK-181 is a low-activation ferritic/martensitic steel that is an attractive candidate for in-core component materials for both fast reactors and fusion reactors. To assess the effect of microstructural engineering on radiation response, two variants of EK-181 were studied: one in an annealed condition and the other subject to severe plastic deformation. These specimens were irradiated with 3.5 MeV Fe self-ions up to 400 peak displacements per atom (dpa) at temperatures ranging from 400 °C to 500 °C. The deformation did not suppress swelling over the whole irradiated region. Instead, deformed samples showed higher swelling in the near-surface region. Void swelling was found to be correlated with grain boundary instability. Significant grain growth occurred when steady-state void growth started.

AB - EK-181 is a low-activation ferritic/martensitic steel that is an attractive candidate for in-core component materials for both fast reactors and fusion reactors. To assess the effect of microstructural engineering on radiation response, two variants of EK-181 were studied: one in an annealed condition and the other subject to severe plastic deformation. These specimens were irradiated with 3.5 MeV Fe self-ions up to 400 peak displacements per atom (dpa) at temperatures ranging from 400 °C to 500 °C. The deformation did not suppress swelling over the whole irradiated region. Instead, deformed samples showed higher swelling in the near-surface region. Void swelling was found to be correlated with grain boundary instability. Significant grain growth occurred when steady-state void growth started.

UR - http://www.scopus.com/inward/record.url?scp=85012202939&partnerID=8YFLogxK

U2 - 10.1016/j.jnucmat.2017.02.006

DO - 10.1016/j.jnucmat.2017.02.006

M3 - Article

AN - SCOPUS:85012202939

VL - 487

SP - 96

EP - 104

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

ER -

ID: 16948313