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Tensile properties and microstructure of Zr-1.8Nb alloy subjected to 140-MeV C4+ ion irradiation
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.; Abe, H.; Yang, HL; Kano, S (reprint author), Univ Tokyo, Grad Sch Engn, Dept Nucl Engn, 2-22 Shirakata Shirane, Tokai, Ibaraki 3191188, Japan.
2017-11-01
发表期刊ELSEVIER SCIENCE BV
ISSN0022-3115
卷号495页码:138-145
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.
部门归属[yang, h. l. ; kano, s. ; shen, j. j. ; zhao, z. s. ; chen, d. y. ; murakami, k. ; abe, h.] univ tokyo, grad sch engn, dept nucl engn, 2-22 shirakata shirane, tokai, ibaraki 3191188, japan ; [matsukawa, y. ; satoh, y.] tohoku univ, inst mat res, 2-1-1 katahira, sendai, miyagi 9808577, japan ; [duan, z. g.] tohoku univ, grad sch engn, 2-1-1 katahira, sendai, miyagi 9808577, japan ; [murakami, k.] nagaoka univ technol, kamitomioka 1603-1, nagaoka, niigata 9402188, japan ; [li, y. f.] chinese acad sci, inst met res, shenyang 110016, liaoning, peoples r china
关键词Zr-nb Alloy High Energy Ion irradiatIon Dislocation Loops Mechanical Properties Strengthening
学科领域Materials Science, Multidisciplinary ; Nuclear Science & Technology
资助者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
收录类别SCI
语种英语
文献类型期刊论文
条目标识符http://ir.imr.ac.cn/handle/321006/79018
专题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.
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