中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
首页 机构 成果 学者
  
  1. CAS IR Grid
  2. 金属研究所
  3. 中国科学院金属研究所
Tensile properties and microstructure of Zr-1.8Nb alloy subjected to 140-MeV C4+ ion irradiation

文献类型：期刊论文

作者Yang, H. L.; Kano, S.; Matsukawa, Y.; Shen, J. J.; Zhao, Z. S.; Duan, Z. G.; Chen, D. Y.; Murakami, K.; Li, Y. F.; Satoh, Y.
刊名ELSEVIER SCIENCE BV
出版日期2017-11-01
卷号495页码:138-145
ISSN号0022-3115
关键词Zr-nb Alloy High Energy Ion irradiatIon Dislocation Loops Mechanical Properties Strengthening
英文摘要Tensile properties and microstructure of a Zr-1.8Nb alloy subjected to 140-MeV C4+ ion irradiation at 573 K up to 5.3 dpa have been investigated by using 0.18 mm-thick tensile specimens. Irradiation damage was introduced into the tensile specimens homogeneously over entire thickness using a variable energy degrader. Irradiation-induced strengthening and embrittlement ( loss of ductility) were successfully evaluated. The yield strength of irradiated specimens (3.1-and 5.3-dpa) was 137% and 145% of unirradiated specimen, whereas the total elongation of those irradiated specimens was less than a half of unirradiated specimen. It appears that the rate of embrittlement is fairly faster than the rate of strengthening. Transmission electron microscopy (TEM) observation on the 3.1-dpa specimen revealed that the bcc-Nb/Zr precipitates originally contained in the alloy were stable in terms of crystal structure and size. The size and number density of dislocation loops were 7.2 nm and 1.2 x 10(21)/m(3) for the loops, 15.4 nm and 6.5 x 10(20)/m(3) for the -type loops, respectively. The increase of yield strength expected from these dislocation loops was similar to 64% of the actual irradiation-induced strengthening, indicating that the dislocation loops are the main contributors for the irradiation-induced strengthening. (C) 2017 Elsevier B.V. All rights reserved.; Tensile properties and microstructure of a Zr-1.8Nb alloy subjected to 140-MeV C4+ ion irradiation at 573 K up to 5.3 dpa have been investigated by using 0.18 mm-thick tensile specimens. Irradiation damage was introduced into the tensile specimens homogeneously over entire thickness using a variable energy degrader. Irradiation-induced strengthening and embrittlement ( loss of ductility) were successfully evaluated. The yield strength of irradiated specimens (3.1-and 5.3-dpa) was 137% and 145% of unirradiated specimen, whereas the total elongation of those irradiated specimens was less than a half of unirradiated specimen. It appears that the rate of embrittlement is fairly faster than the rate of strengthening. Transmission electron microscopy (TEM) observation on the 3.1-dpa specimen revealed that the bcc-Nb/Zr precipitates originally contained in the alloy were stable in terms of crystal structure and size. The size and number density of dislocation loops were 7.2 nm and 1.2 x 10(21)/m(3) for the loops, 15.4 nm and 6.5 x 10(20)/m(3) for the -type loops, respectively. The increase of yield strength expected from these dislocation loops was similar to 64% of the actual irradiation-induced strengthening, indicating that the dislocation loops are the main contributors for the irradiation-induced strengthening. (C) 2017 Elsevier B.V. All rights reserved.
学科主题Materials Science, Multidisciplinary ; Nuclear Science & Technology
语种英语
资助机构project "Study on hydrogenation and radiation effects in advanced nuclear fuel cladding materials" under the Strategic Promotion Program for Basic Nuclear Research; project "The development of nuclear fuel cladding with self-healing intelligence" under the Center of World Intelligence Project for Nuclear S&T and Human Resource Development by Ministry of Education, Culture, Sport, Science and Technology of Japan
公开日期2018-01-10
源URL[http://ir.imr.ac.cn/handle/321006/79018]  
专题金属研究所_中国科学院金属研究所
通讯作者Yang, HL; Kano, S (reprint author), Univ Tokyo, Grad Sch Engn, Dept Nucl Engn, 2-22 Shirakata Shirane, Tokai, Ibaraki 3191188, Japan.
推荐引用方式
GB/T 7714		 Yang, H. L.,Kano, S.,Matsukawa, Y.,et al. Tensile properties and microstructure of Zr-1.8Nb alloy subjected to 140-MeV C4+ ion irradiation[J]. ELSEVIER SCIENCE BV,2017,495:138-145.
APA Yang, H. L..,Kano, S..,Matsukawa, Y..,Shen, J. J..,Zhao, Z. S..,...&Kano, S .(2017).Tensile properties and microstructure of Zr-1.8Nb alloy subjected to 140-MeV C4+ ion irradiation.ELSEVIER SCIENCE BV,495,138-145.
MLA Yang, H. L.,et al."Tensile properties and microstructure of Zr-1.8Nb alloy subjected to 140-MeV C4+ ion irradiation".ELSEVIER SCIENCE BV 495(2017):138-145.

入库方式： OAI收割

来源：金属研究所

浏览0
下载0
收藏0
其他版本

除非特别说明，本系统中所有内容都受版权保护，并保留所有权利。