Radiation response of oxide-dispersion-strengthened alloy MA956 after self-ion irradiation

被引：16

作者：

Chen, Tianyi ^{[1
]}

Kim, Hyosim ^{[1
]}

Gigax, Jonathan G. ^{[1
]}

Chen, Di ^{[1
]}

Wei, Chao-Chen ^{[2
]}

Garner, F. A. ^{[1
,3
]}

Shao, Lin ^{[1
,2
]}

机构：

[1] Texas A&M Univ, Dept Nucl Engn, 205E AIEN Bldg, College Stn, TX 77843 USA

[2] Texas A&M Univ, Dept Mat Sci & Engn, College Stn, TX 77843 USA

[3] Radiat Effects Consulting, Richland, WA 99354 USA

来源：

NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS | 2017年 / 409卷

关键词：

Void swelling; ODS; Ion irradiation; Interface; DAMAGE LEVELS; PURE IRON; STABILITY; DPA; MICROSTRUCTURE; REACTORS; STEELS; T91;

D O I：

10.1016/j.nimb.2017.05.024

中图分类号：

TH7 [仪器、仪表];

学科分类号：

0804 ; 080401 ; 081102 ;

摘要：

We studied the radiation-induced microstructural evolution of an oxide-dispersion-strengthened (ODS) ferritic alloy, MA956, to 180 dpa using 3.5 MeV Fe2+ ions. Post-irradiation examination showed that voids formed rather early and almost exclusively at the particle-matrix interfaces. Surprisingly, voids formed even in the injected interstitial zone. Comparisons with studies on other ODS alloys with smaller and largely coherent dispersoids irradiated at similar conditions revealed that the larger and not completely coherent oxide particles in MA956 serve as defect collectors which promote nucleation of voids at their interface. The interface configuration, which is related to particle type, crystal structure and size, is one of the important factors determining the defect-sink properties of particle-matrix interfaces. (C) 2017 Published by ElsevierB.V.

引用

页码：259 / 263

页数：5

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