Response of 9Cr-ODS steel to proton irradiation at 400 °C

被引：29

作者：

He, Jianchao ^{[1
,2
]}

Wan, Farong ^{[1
]}

Sridharan, Kumar ^{[2
]}

Allen, Todd R. ^{[2
,3
]}

Certain, A. ^{[4
]}

Wu, Y. Q. ^{[5
,6
]}

机构：

[1] Univ Sci & Technol Beijing, Sch Mat Sci & Engn, Beijing 100083, Peoples R China

[2] Univ Wisconsin, Dept Engn Phys, Madison, WI 53706 USA

[3] EG&G Idaho Inc, Idaho Natl Engn Lab, Idaho Falls, ID 83401 USA

[4] Pacific NW Natl Lab, Richland, WA 99354 USA

[5] Boise State Univ, Dept Mat Sci & Engn, Boise, ID 83725 USA

[6] Ctr Adv Energy Studies, Idaho Falls, ID 83401 USA

来源：

JOURNAL OF NUCLEAR MATERIALS | 2014年 / 452卷 / 1-3期

基金：

中国国家自然科学基金;

关键词：

OXIDE PARTICLES; ATOM-PROBE; DISPERSION; STABILITY; NANOCLUSTERS; SEGREGATION; EVOLUTION; BEHAVIOR;

D O I：

10.1016/j.jnucmat.2014.05.004

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The stability of Y-Ti-O nanoclusters, dislocation structure, and grain boundary segregation in 9Cr-ODS steels has been investigated following proton irradiation at 400 degrees C with damage levels up to 3.7 dpa. A slight coarsening and a decrease in number density of nanoclusters were observed as a result of irradiation. The composition of nanoclusters was also observed to change with a slight increase of Y and Cr concentration in the nanoclusters following irradiation. Size, density, and composition of the nanoclusters were investigated as a function of nanocluster size, specifically classified to three groups. In addition to the changes in nanoclusters, dislocation loops were observed after irradiation. Finally, radiation-induced enrichment of Cr and depletion of W were observed at grain boundaries after irradiation. (C) 2014 Elsevier B. V. All rights reserved.

引用

页码：87 / 94

页数：8

共 50 条

[1] Response of nanoclusters in a 9Cr ODS steel to 1 dpa, 525 °C proton irradiation
Certain, A. G.
Field, K. G.
Allen, T. R.
Miller, M. K.
Bentley, J.
Busby, J. T.
JOURNAL OF NUCLEAR MATERIALS, 2010, 407 (01) : 2 - 9
[2] Effect of silicon on oxidation behavior of 9Cr-ODS steel at 650 °C
Xu, Zhiyuan
Liu, Shaojun
Song, Liangliang
Yang, Xinyi
Zhao, Yanyun
Mao, Xiaodong
FUSION ENGINEERING AND DESIGN, 2021, 167
[3] Effect of Ageing Treatment at 650 °C on Microstructure and Properties of 9Cr-ODS Steel
Peng Yanyan
Yu Liming
Liu Yongchang
Ma Zongqing
Liu Chenxi
Li Chong
Li Huijun
ACTA METALLURGICA SINICA, 2020, 56 (08) : 1075 - 1083
[4] Investigation of the cause of peculiar irradiation behavior of 9Cr-ODS steel in BOR-60 irradiation tests
Ohtsuka, Satoshi
Kaito, Takeji
Yano, Yasuhide
Yamashita, Shinichiro
Ogawa, Ryuichiro
Uwaba, Tomoyuki
Koyama, Shinichi
Tanaka, Kenya
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2013, 50 (05) : 470 - 480
[5] Stability of oxide particles under electron irradiation in a 9Cr ODS steel at 400 °C
Li, Feng
Abe, Hiroaki
Ishizaki, Takahiro
Li, Yanfen
Nagasaka, Takuya
Muroga, Takeo
Nagase, Takeshi
Yasuda, Hidehiro
JOURNAL OF NUCLEAR MATERIALS, 2014, 455 (1-3) : 724 - 727
[6] Oxide particle-dislocation interaction in 9Cr-ODS steel
Ijiri, Yuta
Oono, N.
Ukai, S.
Ohtsuka, S.
Kaito, T.
Matsukawa, Y.
NUCLEAR MATERIALS AND ENERGY, 2016, 9 : 378 - 382
[7] Mechanical alloying process of atomized 9Cr-ODS steel powders
Lü, Z. (luz@atm.neu.edu.cn), 1600, Editorial Office of Transactions of Materials and Heat Treatment (35):
[8] 9Cr-ODS steel composite material reinforced by Ta layers
Suo, Jinping (jinpingsuo@hust.edu.cn), 1600, Elsevier Ltd (682):
[9] 9Cr-ODS steel composite material reinforced by Ta layers
Zhang, Ying
Ouyang, Taoyuan
Liu, Dawei
Du, Jingyuan
Wang, Yan
Zhang, Cheng
Suo, Jinping
JOURNAL OF ALLOYS AND COMPOUNDS, 2016, 682 : 294 - 301
[10] Creep constitutive equation of dual phase 9Cr-ODS steel
Sakasegawa, Hideo
Ukai, Shigeharu
Tamura, Manabu
Ohtsuka, Satoshi
Tanigawa, Hiroyasu
Ogiwara, Hiroyuki
Kohyama, Akira
Fujiwara, Masayuki
JOURNAL OF NUCLEAR MATERIALS, 2008, 373 (1-3) : 82 - 89

← 1 2 3 4 5 →