Development of a numerical model for simulating stress corrosion cracking in spent nuclear fuel canisters

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作者
Xin Wu
Fengwen Mu
Scott Gordon
David Olson
Stephen Liu
Zeev Shayer
Zhenzhen Yu
机构
[1] School of Chemical Engineering and Technology,
[2] Sun Yat-Sen University,undefined
[3] Zhuhai,undefined
[4] George S. Ansell Department of Metallurgical and Materials Engineering,undefined
[5] Colorado School of Mines,undefined
[6] High-Frequency High-Voltage Device and Integrated Circuits R&D Center,undefined
[7] Institute of Microelectronics of Chinese Academy of Sciences,undefined
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Prediction and detection of the chloride-induced stress corrosion cracking (CISCC) in Type 304 stainless steel spent nuclear fuel canisters are vital for the lifetime extension of dry storage canisters. This paper conducts a critical review that focuses on the numerical modeling and simulation on the research progress of the CISCC. The numerical models emphasizing the residual stress, susceptible microstructure, and corrosive environment are summarized individually. Meanwhile, the simulation studies on the role of hydrogen-assisted cracking are reviewed. Finally, a multi-physical numerical model, which combines the different fields is proposed based on our recent investigation.
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