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首页> 外文期刊>Corrosion: The Journal of Science and Engineering >Irradiation-Assisted Stress Corrosion Cracking and Impact on Life Extension
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Irradiation-Assisted Stress Corrosion Cracking and Impact on Life Extension

机译：Irradiation-Assisted Stress Corrosion Cracking and Impact on Life Extension

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The paper aims to give a present status of knowledge on irradiation-assisted stress corrosion cracking (IASCC) from the point of view of nuclear power plant life extension. Field experience as well as laboratory test results are considered to illustrate how IASCC already impacts plant operation. IASCC has been differentiated with difficulty from standard integran-ular stress corrosion cracking (IGSCC), but above a threshold radiation dose, an enhanced portion of intergranular fracture are convincing evidences for IASCC. IASCC cracking in boiling water reactor (BWR) core shrouds started wide studies of materials of irradiated reactor internals. The last cases of IASCC have been found in pressurized water reactor/water-water energy reactor (PWR/WWER) baffle bolts. Laboratory slow strain rate tests as well as constant load and crack growth rate tests in simulated BWR and PWR environments resulted in the discovery of the IASCC threshold dose, the threshold stress, and that the cracking kinetics increase with neutron exposure. The present understanding of the mechanism of IASCC in BWR/PWR systems is given assuming no fundamental differences between the two environments. Localized deformation on grain boundaries affected by segregation and environmental effects is the most likely mechanism. Finally, plant life extensions likely will bring an increase of IASCC risk because of higher accumulated doses. The impact on BWR and PWR internal components is estimated and discussed. It is concluded that further critical experiments and complex data analyses are urgently needed.

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