Investigation of the thermo-mehcanical behavior of neutron-irradiated Fe-Cr alloys by self-consistent plasticity theory

Research output: Contribution to journalArticle

Standard

Investigation of the thermo-mehcanical behavior of neutron-irradiated Fe-Cr alloys by self-consistent plasticity theory. / Xiao, Xiazi; Terentyev, Dmitry; Bakaev, Alexander; Yu, Long; Jin, Zhaohui; Duan, Huiling.

In: Journal of Nuclear Materials, Vol. 477, 15.08.2016, p. 123-133.

Research output: Contribution to journalArticle

Author

Xiao, Xiazi ; Terentyev, Dmitry ; Bakaev, Alexander ; Yu, Long ; Jin, Zhaohui ; Duan, Huiling. / Investigation of the thermo-mehcanical behavior of neutron-irradiated Fe-Cr alloys by self-consistent plasticity theory. In: Journal of Nuclear Materials. 2016 ; Vol. 477. pp. 123-133.

Bibtex - Download

@article{878337dfe0864cde86291785e74edf00,
title = "Investigation of the thermo-mehcanical behavior of neutron-irradiated Fe-Cr alloys by self-consistent plasticity theory",
abstract = "The thermo-mechanical behavior of non-irradiated (at 223 K, 302 K and 573 K) and neutron irradiated (at 573 K) Fe-2.5Cr, Fe-5Cr and Fe-9Cr alloys is studied by a self-consistent plasticity theory, which consists of constitutive equations describing the contribution of radiation defects at grain level, and the elasticviscoplastic self-consistent method to obtain polycrystalline behaviors. Attention is paid to two types of radiation-induced defects: interstitial dislocation loops and solute rich clusters, which are believed to be the main sources of hardening in Fe-Cr alloys at medium irradiation doses. Both the hardening mechanism and microstructural evolution are investigated by using available experimental data on microstructures, and implementing hardening rules derived from atomistic data. Good agreement with experimental data is achieved for both the yield stress and strain hardening of non-irradiated and irradiated Fe-Cr alloys by treating dislocation loops as strong thermally activated obstacles and solute rich clusters as weak shearable ones.",
keywords = "iron alloys, Irradiation effect, defects, continuum mechanics model, mechanical behavior",
author = "Xiazi Xiao and Dmitry Terentyev and Alexander Bakaev and Long Yu and Zhaohui Jin and Huiling Duan",
note = "Score=10",
year = "2016",
month = "8",
day = "15",
doi = "10.1016/j.jnucmat.2016.05.012",
language = "English",
volume = "477",
pages = "123--133",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier",

}

RIS - Download

TY - JOUR

T1 - Investigation of the thermo-mehcanical behavior of neutron-irradiated Fe-Cr alloys by self-consistent plasticity theory

AU - Xiao, Xiazi

AU - Terentyev, Dmitry

AU - Bakaev, Alexander

AU - Yu, Long

AU - Jin, Zhaohui

AU - Duan, Huiling

N1 - Score=10

PY - 2016/8/15

Y1 - 2016/8/15

N2 - The thermo-mechanical behavior of non-irradiated (at 223 K, 302 K and 573 K) and neutron irradiated (at 573 K) Fe-2.5Cr, Fe-5Cr and Fe-9Cr alloys is studied by a self-consistent plasticity theory, which consists of constitutive equations describing the contribution of radiation defects at grain level, and the elasticviscoplastic self-consistent method to obtain polycrystalline behaviors. Attention is paid to two types of radiation-induced defects: interstitial dislocation loops and solute rich clusters, which are believed to be the main sources of hardening in Fe-Cr alloys at medium irradiation doses. Both the hardening mechanism and microstructural evolution are investigated by using available experimental data on microstructures, and implementing hardening rules derived from atomistic data. Good agreement with experimental data is achieved for both the yield stress and strain hardening of non-irradiated and irradiated Fe-Cr alloys by treating dislocation loops as strong thermally activated obstacles and solute rich clusters as weak shearable ones.

AB - The thermo-mechanical behavior of non-irradiated (at 223 K, 302 K and 573 K) and neutron irradiated (at 573 K) Fe-2.5Cr, Fe-5Cr and Fe-9Cr alloys is studied by a self-consistent plasticity theory, which consists of constitutive equations describing the contribution of radiation defects at grain level, and the elasticviscoplastic self-consistent method to obtain polycrystalline behaviors. Attention is paid to two types of radiation-induced defects: interstitial dislocation loops and solute rich clusters, which are believed to be the main sources of hardening in Fe-Cr alloys at medium irradiation doses. Both the hardening mechanism and microstructural evolution are investigated by using available experimental data on microstructures, and implementing hardening rules derived from atomistic data. Good agreement with experimental data is achieved for both the yield stress and strain hardening of non-irradiated and irradiated Fe-Cr alloys by treating dislocation loops as strong thermally activated obstacles and solute rich clusters as weak shearable ones.

KW - iron alloys

KW - Irradiation effect

KW - defects

KW - continuum mechanics model

KW - mechanical behavior

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/22132406

U2 - 10.1016/j.jnucmat.2016.05.012

DO - 10.1016/j.jnucmat.2016.05.012

M3 - Article

VL - 477

SP - 123

EP - 133

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

ER -

ID: 2179192