Ion-irradiation induced hardening behavior of zirconium alloys: A combination of experimental and theoretical study

被引:6
作者
Xia, Liang [1 ]
Liu, Kai [2 ]
Cao, Yucheng [3 ]
Jiang, Chao [3 ]
机构
[1] Peking Univ, Sch Phys, State Key Lab Nucl Phys & Technol, Beijing 100871, Peoples R China
[2] Changsha Univ Sci & Technol, Coll Automot & Mech Engn, Changsha 410114, Peoples R China
[3] Hunan Univ, Coll Mech & Vehicle Engn, State Key Lab Adv Design & Mfg Vehicle Body, Changsha 410082, Peoples R China
关键词
Ion-irradiation; Zirconium alloys; Nano-indentation test; Theoretical analysis; TRANSMISSION ELECTRON-MICROSCOPY; 2ND PHASE PARTICLES; 350; DEGREES-C; MECHANICAL-PROPERTIES; PURE ZR; REACTOR CORROSION; NANO-INDENTATION; GRAIN-SIZE; NB; MODEL;
D O I
10.1016/j.ijrmhm.2023.106432
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
This study aimed to investigate the microstructure information and mechanical behavior of ion-irradiated zirconium (Zr) alloys through a combination of experimental measurements and theoretical analysis. Experimental procedures involved Au3+ irradiation of Zr-1.5Sn-0.2Fe-0.1Cr and Zr-1.0Sn-1.0Nb-0.1Fe at 3 displacements per atom (dpa) and 30 dpa. Transmission electron microscopy analysis revealed the formation of precipitates such as Zr(Fe, Cr)2 in Zr-1.5Sn-0.2Fe-0.1Cr, as well as beta-Nb and Zr(Nb, Fe)2 in Zr-1.0Sn-1.0Nb-0.1Fe. These precipitates exhibited a transformation from crystalline state to partial or complete amorphization after ion-irradiation. Furthermore, macroscopic mechanical properties of the Zr alloys were characterized by nano-indentation tests, which revealed a significant indentation size effect (ISE) and irradiation hardening behavior. To provide a theoretical understanding of the depth-dependent hardness observed in ion-irradiated Zr alloys, a mechanistic model was developed to address the different expansion rates of the plastic zone in the irradiated and unirradiated region. The results indicated that the ISE phenomenon could be attributed to the reduction in the density of geometrically necessary dislocations (GNDs) caused by the expansion of the plastic zone. In addition, the irradiation hardening behavior primarily resulted from the contribution of irradiation-induced defects. With increasing indentation depth, the dominant hardening mechanisms changed from the contribution of irradiationinduced defects, GNDs and statistically stored dislocations (SSDs) in the irradiated region to SSDs in the unirradiated substrate.
引用
收藏
页数:17
相关论文
共 72 条
[1]   The corrosion of Zr(Fe, Cr)2 and Zr2Fe secondary phase particles in Zircaloy-4 under 350 °C pressurised water conditions [J].
Annand, Kirsty ;
Nord, Magnus ;
MacLaren, Ian ;
Gass, Mhairi .
CORROSION SCIENCE, 2017, 128 :213-223
[2]   PRECIPITATION HARDENING [J].
ARDELL, AJ .
METALLURGICAL TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 1985, 16 (12) :2131-2165
[3]  
Arias D., 1988, Bulletin of Alloy Phase Diagrams, V9, P597, DOI DOI 10.1007/BF02881963
[4]   Irradiation hardening of advanced tungsten grades: An experimental and inverse finite element method study [J].
Bakaev, Alexander ;
Terentyev, Dmitry ;
Zinovev, Aleksandr ;
Zhurkin, Evgeny E. .
INTERNATIONAL JOURNAL OF REFRACTORY METALS & HARD MATERIALS, 2022, 105
[5]   A dislocation-based constitutive law for pure Zr including temperature effects [J].
Beyerlein, I. J. ;
Tome, C. N. .
INTERNATIONAL JOURNAL OF PLASTICITY, 2008, 24 (05) :867-895
[6]   Application of In Situ TEM to Investigate Irradiation Creep in Nanocrystalline Zirconium [J].
Bufford, Daniel C. ;
Barr, Christopher M. ;
Wang, Baoming ;
Hattar, Khalid ;
Haque, Aman .
JOM, 2019, 71 (10) :3350-3357
[7]   Glide and cross-slip of a-dislocations in Zr and Ti [J].
Caillard, D. ;
Gaume, M. ;
Onimus, F. .
ACTA MATERIALIA, 2018, 155 :23-34
[8]   The role of primary α grains in the degree of transformation texture obeying the Burgers orientation relationship in Zr alloys [J].
Cao, Yucheng ;
Wu, Tianxian ;
Xia, Liang ;
Feng, Pengfei ;
Jiang, Chao ;
Chen, Ding .
INTERNATIONAL JOURNAL OF REFRACTORY METALS & HARD MATERIALS, 2022, 107
[9]   Irradiation-induced swelling and hardening in HfNbTaTiZr refractory high-entropy alloy [J].
Chang, Stanley ;
Tseng, Ko-Kai ;
Yang, Tzu-Yi ;
Chao, Der-Sheng ;
Yeh, Jien-Wei ;
Liang, Jenq-Horng .
MATERIALS LETTERS, 2020, 272
[10]   Some thoughts on the mechanisms of in-reactor corrosion of zirconium alloys [J].
Cox, B .
JOURNAL OF NUCLEAR MATERIALS, 2005, 336 (2-3) :331-368