Characterization of ion beam irradiated 304 stainless steel utilizing nanoindentation and Laue microdiffraction

A. Lupinacci; K. Chen; Y. Li; M. Kunz; Z. Jiao; G. S. Was; M. D. Abad; A. M. Minor; P. Hosemann

doi:10.1016/j.jnucmat.2014.11.050

Characterization of ion beam irradiated 304 stainless steel utilizing nanoindentation and Laue microdiffraction

A. Lupinacci, K. Chen, Y. Li, M. Kunz, Z. Jiao, G. S. Was, M. D. Abad, A. M. Minor, P. Hosemann

Producció científica: Article en revista indexada › Article › Avaluat per experts

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Characterizing irradiation damage in materials utilized in light water reactors is critical for both material development and application reliability. Here we use both nanoindentation and Laue microdiffraction to characterize both the mechanical response and microstructure evolution due to irradiation. Two different irradiation conditions were considered in 304 stainless steel: 1 dpa and 10 dpa. In addition, an annealed condition of the 10 dpa specimen for 1 h at 500 °C was evaluated. Nanoindentation revealed an increase in hardness due to irradiation and also revealed that hardness saturated in the 10 dpa case. Broadening using Laue microdiffraction peaks indicates a significant plastic deformation in the irradiated area that is in good agreement with both the SRIM calculations and the nanoindentation results.

Idioma original	Anglès
Pàgines (de-a)	70-76
Nombre de pàgines	7
Revista	Journal of Nuclear Materials
Volum	458
DOIs	https://doi.org/10.1016/j.jnucmat.2014.11.050
Estat de la publicació	Publicada - de març 2015
Publicat externament	Sí

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10.1016/j.jnucmat.2014.11.050

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@article{cfc7d2fd75fb4400833eff174f3254d4,

title = "Characterization of ion beam irradiated 304 stainless steel utilizing nanoindentation and Laue microdiffraction",

abstract = "Characterizing irradiation damage in materials utilized in light water reactors is critical for both material development and application reliability. Here we use both nanoindentation and Laue microdiffraction to characterize both the mechanical response and microstructure evolution due to irradiation. Two different irradiation conditions were considered in 304 stainless steel: 1 dpa and 10 dpa. In addition, an annealed condition of the 10 dpa specimen for 1 h at 500 °C was evaluated. Nanoindentation revealed an increase in hardness due to irradiation and also revealed that hardness saturated in the 10 dpa case. Broadening using Laue microdiffraction peaks indicates a significant plastic deformation in the irradiated area that is in good agreement with both the SRIM calculations and the nanoindentation results.",

keywords = "Stress-corrosion cracking, Mechanical-properties, Structural-materials, Stainless-steels, Hardness, Electromigration, Reactors, Fission, Protons, Fusion",

author = "A. Lupinacci and K. Chen and Y. Li and M. Kunz and Z. Jiao and Was, {G. S.} and Abad, {M. D.} and Minor, {A. M.} and P. Hosemann",

note = "Funding Information: The ALS is supported by the Director, Office of Science, DOE-BES, Materials Science Division , under Contract No. DE-AC02-05CH11231 at LBNL. Additional support for ALS beam line 12.3.2 comes from NSF ( 0416243 ). KC acknowledges the support from the National Young 1000 Talents Program of China . We want to thank EPRI for supporting this research as well as DOE-NEUP under the award DE-FOA-0000799 Publisher Copyright: {\textcopyright} 2014 Elsevier B.V. All rights reserved.",

year = "2015",

month = mar,

doi = "10.1016/j.jnucmat.2014.11.050",

language = "English",

volume = "458",

pages = "70--76",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier",

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TY - JOUR

T1 - Characterization of ion beam irradiated 304 stainless steel utilizing nanoindentation and Laue microdiffraction

AU - Lupinacci, A.

AU - Chen, K.

AU - Li, Y.

AU - Kunz, M.

AU - Jiao, Z.

AU - Was, G. S.

AU - Abad, M. D.

AU - Minor, A. M.

AU - Hosemann, P.

N1 - Funding Information: The ALS is supported by the Director, Office of Science, DOE-BES, Materials Science Division , under Contract No. DE-AC02-05CH11231 at LBNL. Additional support for ALS beam line 12.3.2 comes from NSF ( 0416243 ). KC acknowledges the support from the National Young 1000 Talents Program of China . We want to thank EPRI for supporting this research as well as DOE-NEUP under the award DE-FOA-0000799 Publisher Copyright: © 2014 Elsevier B.V. All rights reserved.

PY - 2015/3

Y1 - 2015/3

N2 - Characterizing irradiation damage in materials utilized in light water reactors is critical for both material development and application reliability. Here we use both nanoindentation and Laue microdiffraction to characterize both the mechanical response and microstructure evolution due to irradiation. Two different irradiation conditions were considered in 304 stainless steel: 1 dpa and 10 dpa. In addition, an annealed condition of the 10 dpa specimen for 1 h at 500 °C was evaluated. Nanoindentation revealed an increase in hardness due to irradiation and also revealed that hardness saturated in the 10 dpa case. Broadening using Laue microdiffraction peaks indicates a significant plastic deformation in the irradiated area that is in good agreement with both the SRIM calculations and the nanoindentation results.

AB - Characterizing irradiation damage in materials utilized in light water reactors is critical for both material development and application reliability. Here we use both nanoindentation and Laue microdiffraction to characterize both the mechanical response and microstructure evolution due to irradiation. Two different irradiation conditions were considered in 304 stainless steel: 1 dpa and 10 dpa. In addition, an annealed condition of the 10 dpa specimen for 1 h at 500 °C was evaluated. Nanoindentation revealed an increase in hardness due to irradiation and also revealed that hardness saturated in the 10 dpa case. Broadening using Laue microdiffraction peaks indicates a significant plastic deformation in the irradiated area that is in good agreement with both the SRIM calculations and the nanoindentation results.

KW - Stress-corrosion cracking

KW - Mechanical-properties

KW - Structural-materials

KW - Stainless-steels

KW - Hardness

KW - Electromigration

KW - Reactors

KW - Fission

KW - Protons

KW - Fusion

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VL - 458

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JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

ER -

Characterization of ion beam irradiated 304 stainless steel utilizing nanoindentation and Laue microdiffraction

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