The influence of solid solution hydrogen and precipitated hydride on the creep behavior of Zircaloy-4

被引:0
作者
Kim, Ho -A [1 ]
Choi, Sungjun [1 ]
Kim, Yong-Soo [1 ]
Park, Jiwon [2 ]
Kang, Joo-Hee [3 ]
Kim, Sangtae [1 ,4 ]
机构
[1] Hanyang Univ, Dept Nucl Engn, 222 Wangsimni Ro, Seoul 04763, South Korea
[2] Korea Inst Mat Sci, Aerosp Mat Ctr, 797 Changwondaero, Chang Won 51508, Gyeongnam, South Korea
[3] Korea Inst Mat Sci, Dept Mat Anal, 797 Changwondaero, Chang Won 51508, Gyeongnam, South Korea
[4] Hanyang Univ, Dept Mat Sci & Engn, 222 Wangsimni Ro, Seoul 04763, South Korea
基金
新加坡国家研究基金会;
关键词
Thermal creep; Zirconium hydride; Spent nuclear fuel (SNF) cladding; Microstructure; Electron backscatter diffraction (EBSD); STACKING-FAULT ENERGY; DELTA-HYDRIDE; GRAIN-SIZE; ASSISTED CRACKING; THERMAL CREEP; NUCLEAR-FUEL; DRY STORAGE; DEFORMATION; ZIRCONIUM; MECHANISMS;
D O I
10.1016/j.jnucmat.2024.155244
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The effect of hydrogen on the creep rates of Zircaloy-4 claddings especially in the low hydrogen concentration remains largely unexplored while creep is considered a main mechanism for spent nuclear fuel failure along with hydride-induced mechanisms. Here, we study the influence of hydrogen on the creep behavior of low burnup Zircaloy-4 cladding from a microstructural perspective. The creep tests at 450 degrees C and 120 MPa reveal that specimens with hydrogen contents below the terminal solid solubility for dissolution (TSSD) at the test temperature exhibited decreased creep resistance as hydrogen concentration increased, while those with hydrogen contents above the TSSD demonstrated increased creep resistance with higher hydrogen concentration. The lowest creep resistance occurs at the hydrogen concentration corresponding to the TSSD. Additional microstructural analyses using electron backscattered diffraction (EBSD) show the increasing intra-granular/intergranular hydride ratio in the post-crept specimens as the hydrogen concentration decreases, suggesting that hydrogen atoms in solid solution aid creep progression. Also, an increased amount of twin boundaries is observed in post-crept specimens with hydrogen concentration above TSSD. These results suggest that creep assessment in spent nuclear fuels may require caution especially in low-burnup regime.
引用
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页数:13
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