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

E. Aydogan; T. Chen; J. G. Gigax; D. Chen; X. Wang; P. S. Dzhumaev; O. V. Emelyanova; M. G. Ganchenkova; B. A. Kalin; M. Leontiva-Smirnova; R. Z. Valiev; N. A. Enikeev; M. M. Abramova; Y. Wu; W. Y. Lo; Y. Yang; M. Short; S. A. Maloy; F. A. Garner; L. Shao

doi:10.1016/j.jnucmat.2017.02.006

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

E. Aydogan
, T. Chen
, J. G. Gigax
, D. Chen
, X. Wang
, P. S. Dzhumaev
, O. V. Emelyanova
, M. G. Ganchenkova
, B. A. Kalin
, M. Leontiva-Smirnova
, R. Z. Valiev
, N. A. Enikeev
, M. M. Abramova
, Y. Wu
, W. Y. Lo
, Y. Yang
, M. Short
, S. A. Maloy
, F. A. Garner
, L. Shao

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

40 Scopus citations

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.

Original language	English
Pages (from-to)	96-104
Number of pages	9
Journal	Journal of Nuclear Materials
Volume	487
DOIs	https://doi.org/10.1016/j.jnucmat.2017.02.006
State	Published - Apr 15 2017
Externally published	Yes

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10.1016/j.jnucmat.2017.02.006

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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

@article{4ef5db9a638c48bfa7dc874b7471a91e,

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 B.V.",

}

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

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 - https://www.scopus.com/pages/publications/85012202939

U2 - 10.1016/j.jnucmat.2017.02.006

DO - 10.1016/j.jnucmat.2017.02.006

M3 - Article

SN - 0022-3115

VL - 487

SP - 96

EP - 104

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

ER -

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

Abstract

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