首页|Fracture mode analysis of Zr-Sn-Nb alloy under simulated LOCA condition in advanced nuclear reactors

Fracture mode analysis of Zr-Sn-Nb alloy under simulated LOCA condition in advanced nuclear reactors

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  • NSTL
  • Elsevier
? 2022The present study focuses on fracture mode of Zr-Sn-Nb cladding material under simulated LOCA condition. The results reveal that the oxidation share between 15% and 20% has little influence on the tensile strength. Microstructure analysis of cross-sectional and fracture morphology demonstrate that the fracture mode of Zr-Sn-Nb alloy oxidized at high temperature includes the brittle rupture of ZrO2, the cleavage fracture of α-Zr(O) layer, and a mixed ductile-brittle fracture of prior-β layer. Zr-Sn-Nb coupons exhibit brittle fracture features with the elongation below 0.34% at room temperature, while the plastic strain increases to ～10% at 350 °C in vacuum. The coupons cooled by water quenching have better tensile strength and worse elongation than those cooled by other modes. It is also found that the prior-β layer is composed of α-Zr phase, δ-Zr1.6 and γ-ZrH precipitates, and the composition can be greatly affected by the cooling modes.

Cooling modeFracture mechanismHigh-temperature oxidationTensile behaviorZirconium alloys

Zhao W.、Song P.、Peng X.、Liao Z.、Xiao H.、Chen L.、Zhang F.、Zhang C.

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Science and Technology on Reactor Fuel and Materials Laboratory Nuclear Power Institute of China

Science and Technology on Thermostructural Composite Materials Laboratory Northwestern Polytechnical University

2022

10.1016/j.engfailanal.2022.106392

Engineering failure analysis

Engineering failure analysis

EISCI
ISSN：1350-6307
年,卷(期)：2022.137
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