Effects of alloying elements (Sn, Nb, Cr, and Mo) on the microstructure and mechanical properties of zirconium alloys

被引:67
作者
Yang, Huilong [1 ]
Shen, Jingjie [1 ]
Matsukawa, Yoshitaka [2 ]
Satoh, Yuhki [2 ]
Kano, Sho [2 ]
Zhao, Zishou [1 ]
Li, Yanfen [2 ]
Li, Feng [1 ]
Abe, Hiroaki [2 ]
机构
[1] Tohoku Univ, Grad Sch Engn, Dept Quantum Sci & Energy Engn, Sendai, Miyagi 9808577, Japan
[2] Tohoku Univ, Inst Mat Res, Sendai, Miyagi 9808577, Japan
关键词
recrystallization; mechanical property; microstructure; fuel cladding; cold-rolling; zirconium alloy; ZR ALLOYS; ALPHA-ZR; FE; BEHAVIOR; TEMPERATURE; SOLUBILITY; EVOLUTION; HARDNESS; GROWTH; CREEP;
D O I
10.1080/00223131.2014.996622
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The alloying effects of Sn, Nb, Cr, and Mo on zirconium alloys were elucidated and compared. Electron backscatter diffraction, transmission electron microscopy, tensile test, and fractographic observation were jointly utilized to carry out detailed microstructural characterization and mechanical property evaluation. Results show that Mo is the most effective among these elements from the viewpoints of strengthening and reducing grain size. The strengthening mechanism for each element is also discussed. The order of solid-solution strengthening of these alloying elements is Cr > Nb > Sn, and the sequence is Cr approximate to Mo > Nb when precipitation strengthening is considered. Further, as far as the ability to impede dislocation motion is concerned, the sequence is Mo > Cr > Nb > Sn. The experimental results demonstrate that minor amount of Mo addition in zirconium alloys is greatly effective in strengthening the alloy and reducing the grain size.
引用
收藏
页码:1162 / 1173
页数:12
相关论文
共 37 条
[1]   A review on the clad failure studies [J].
Alam, Tanweer ;
Khan, Mohd. Kaleem ;
Pathak, Manabendra ;
Ravi, K. ;
Singh, Ritu ;
Gupta, S. K. .
NUCLEAR ENGINEERING AND DESIGN, 2011, 241 (09) :3658-3677
[2]  
[Anonymous], T AIME
[3]   THE SOLUBILITY OF TIN IN ALPHA-ZIRCONIUM AND BETA-ZIRCONIUM BELOW 1000-DEGREES-C [J].
ARIAS, D ;
ROBERTI, L .
JOURNAL OF NUCLEAR MATERIALS, 1983, 118 (2-3) :143-149
[4]   Phase transition temperature in the Zr-rich corner of Zr-Nb-Sn-Fe alloys [J].
Canay, M ;
Danón, CA ;
Arias, D .
JOURNAL OF NUCLEAR MATERIALS, 2000, 280 (03) :365-371
[5]   THE AGING RESPONSE OF ZIRCONIUM-TIN ALLOYS [J].
CARPENTER, GJC ;
IBRAHIM, EF ;
WATTERS, JF .
JOURNAL OF NUCLEAR MATERIALS, 1981, 102 (03) :280-291
[6]   Effect of predeformation on microstructural evolution of a Zr alloy during 550-700 °C aging after β quenching [J].
Chai, Linjiang ;
Luan, Baifeng ;
Murty, Korukonda L. ;
Liu, Qing .
ACTA MATERIALIA, 2013, 61 (08) :3099-3109
[7]   Precipitation and growth study of intermetallics and their effect on oxidation behavior in Zr-Sn-Fe-Cr alloy [J].
Choudhuri, G. ;
Neogy, S. ;
Sen, D. ;
Mazumder, S. ;
Srivastava, D. ;
Dey, G. K. ;
Shah, B. K. .
JOURNAL OF NUCLEAR MATERIALS, 2012, 430 (1-3) :205-215
[8]   Effect of Mo on recrystallization characteristics of Zr-Nb(Sn)-Mo experimental alloys [J].
Chun, YB ;
Hwang, SK ;
Kim, MH ;
Kwun, SI ;
Kim, YS .
JOURNAL OF NUCLEAR MATERIALS, 1999, 265 (1-2) :28-37
[9]   THE COMBINATION OF ATOMIC SIZE AND ELASTIC-MODULUS MISFIT INTERACTIONS IN SOLID-SOLUTION HARDENING [J].
GYPEN, LA ;
DERUYTTERE, A .
SCRIPTA METALLURGICA, 1981, 15 (08) :815-820
[10]   Hall-Petch relation and boundary strengthening [J].
Hansen, N .
SCRIPTA MATERIALIA, 2004, 51 (08) :801-806