کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
1565630 | 1514207 | 2013 | 10 صفحه PDF | دانلود رایگان |
• Steady state crack velocity of delayed hydride cracking in Zircaloy-2 was analyzed.
• A large stress peak is induced at an end of hydride by volume expansion of hydride.
• Hydrogen diffuses to the stress peak, thereby accelerating steady hydride growth.
• Crack velocity was estimated from the calculated hydrogen flux into the stress peak.
• There was good agreement between calculation results and experimental data.
Delayed hydride cracking (DHC) of Zircaloy-2 is one possible mechanism for the failure of boiling water reactor fuel rods in ramp tests at high burnup. Analyses were made for hydrogen diffusion around a crack tip to estimate the crack velocity of DHC in zirconium alloys, placing importance on effects of precipitation of δ-hydride. The stress distribution around the crack tip is significantly altered by precipitation of hydride, which was strictly analyzed using a finite element computer code. Then, stress-driven hydrogen diffusion under the altered stress distribution was analyzed by a differential method. Overlapping of external stress and hydride precipitation at a crack tip induces two stress peaks; one at a crack tip and the other at the front end of the hydride precipitate. Since the latter is larger than the former, more hydrogen diffuses to the front end of the hydride precipitate, thereby accelerating hydride growth compared with that in the absence of the hydride. These results indicated that, after hydride was formed in front of the crack tip, it grew almost steadily accompanying the interaction of hydrogen diffusion, hydride growth and the stress alteration by hydride precipitation. Finally, crack velocity was estimated from the calculated hydrogen flux into the crack tip as a function of temperature, stress intensity factor and material strength. There was qualitatively good agreement between calculation results and experimental data.
Journal: Journal of Nuclear Materials - Volume 439, Issues 1–3, August 2013, Pages 202–211