A structure-property correlation study of neutron irradiation induced damage in EU batch of ODS Eurofer97 steel

被引：22

作者：

Kolluri, M. ^{[1
]}

Edmondson, P. D. ^{[2
]}

Luzginova, N. V. ^{[1
]}

van der Berg, F. A. ^{[1
]}

机构：

[1] Nucl Res & Consultancy Grp NRG, NL-1755 ZG Petten, Netherlands

[2] Univ Oxford, Dept Mat, Oxford OX1 3PH, England

来源：

MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING | 2014年 / 597卷

基金：

英国工程与自然科学研究理事会;

关键词：

ODS Eurofer97 steel; Neutron irradiation damage; Transmission electron microscopy; Dislocation loops; Post-irradiation examination; ACTIVATION FERRITIC/MARTENSITIC STEEL; MECHANICAL-PROPERTIES; MARTENSITIC STEELS; DEGREES-C; BLANKET; DPA; MICROSTRUCTURE; NANOCLUSTERS; DESIGN;

D O I：

10.1016/j.msea.2013.12.074

中图分类号：

TB3 [工程材料学];

学科分类号：

0805 ; 080502 ;

摘要：

Within the framework of the European Fusion Development Agreement (EFDA), an EU batch of oxide-dispersion-strengthened (ODS) Eurofer97 steel samples have been irradiated with neutrons to nominal dose levels of I and 3 displacements per atom (dpa) in the High Flux Reactor (HFR) located in Petten to investigate irradiation induced changes in the microstructure and mechanical properties. The results of the irradiation-induced effects on the mechanical properties of this steel are published by Luzginova et al. (2011) [18]. In this paper, post-irradiation examination (PIE) by Transmission Electron Microscopy is performed on the material irradiated at 300 degrees C to investigate irradiation-induced microstructure dependence on the neutron irradiation dose and relate it to the observed mechanical properties. The results of this study revealed a presence of a high density of black dot damage and self-interstitial atom (SIA) dislocation loops in the microstructure after neutron irradiation to both 1 and 3 dpa dose levels. No dissolution of the ODS particles due to irradiation was observed. These results are discussed in relation with the irradiation hardening and shift in ductile to brittle transition temperature (DBTT) observed in this alloy at the above irradiation conditions. (C) 2013 Elsevier B.V. All rights reserved.

引用

页码：111 / 116

页数：6

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