Cyclic cracking behavior of low-alloy pressure vessel steel in simulated BWR water

Wu, Xiaohu; Katada, Yasuyuki

doi:10.1016/j.jnucmat.2004.03.004

Cited by 3 publications

(2 citation statements)

References 24 publications

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“…It is rather difficult to evaluate the effective crack tip strain rate owing to the singularity in the crack tip stress-strain field. Gabetta's model [31][32][33][34] was used to calculate the crack tip strain rate to confirm that the strain rate is located in the region of dynamic strain aging. Gabetta's model is given below…”

Section: Effects Of Sulphur Content and Dynamic Strain Aging On Fatig...mentioning

confidence: 99%

Effect of dynamic strain aging on fatigue crack growth behaviour of reactor pressure vessel steels

Huang¹,

Yeh²,

Kuo³

et al. 2006

Materials Science and Technology

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Fatigue tests under constant amplitude load were conducted on compact tension specimens of SA533B3 steels with four levels of sulphur content at different temperatures. A modified capacitance type crack opening displacement (COD) gauge was shown to be suitable for fatigue crack length measurement at high temperatures. Test results obtained with different measurement techniques show good consistency. The observation that the Young's moduli measured at a strain rate of 4610 23 s 21 for the SA533B3 steels at 150 and 300uC do not decrease with increasing temperature seems to be related to the presence of dynamic strain aging. The fatigue crack growth rates at 150 and 300uC are about two and half times slower than those tested at 400uC because dynamic strain aging prevails at 150 and 300uC. Fractographic examination results suggest that inclusions embedded in secondary cracks enhanced the fatigue crack initiation rather than the fatigue crack growth.

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Section: Effects Of Sulphur Content and Dynamic Strain Aging On Fatig...mentioning

confidence: 99%

Effect of dynamic strain aging on fatigue crack growth behaviour of reactor pressure vessel steels

Huang¹,

Yeh²,

Kuo³

et al. 2006

Materials Science and Technology

View full text Add to dashboard Cite

show abstract

“…These defects can act as internal hydrogen sources and thus, cause increased embrittlement. Wu and Katada [11][12][13] investigated the low-cycle fatigue behaviour, fatigue crack initiation and growth behaviour of unirradiated low-alloy pressure vessel steel A533B in a simulated BWR (boiling water reactor) environment. They could prove a close strain rate dependence of the cyclic cracking morphologies in high-temperature water, due to a change in the dominant environmentally assisted cracking.…”

Section: Introductionmentioning

confidence: 99%

Influence of hydrogen on the toughness of irradiated reactor pressure vessel steels

Müller

Uhlemann²,

Ulbricht

et al. 2006

Journal of Nuclear Materials

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Effects of dynamic strain aging on mechanical properties of SA508 class 3 reactor pressure vessel steel

Han

et al. 2009

J Mater Sci

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Cyclic cracking behavior of low-alloy pressure vessel steel in simulated BWR water

Cited by 3 publications

References 24 publications

Effect of dynamic strain aging on fatigue crack growth behaviour of reactor pressure vessel steels

Effect of dynamic strain aging on fatigue crack growth behaviour of reactor pressure vessel steels

Influence of hydrogen on the toughness of irradiated reactor pressure vessel steels

Effects of dynamic strain aging on mechanical properties of SA508 class 3 reactor pressure vessel steel

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