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

Author:

Wu XinORCID,Mu FengwenORCID,Gordon Scott,Olson David,Liu Stephen,Shayer Zeev,Yu Zhenzhen

Abstract

AbstractPrediction 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.

Publisher

Springer Science and Business Media LLC

Subject

Materials Chemistry,Materials Science (miscellaneous),Chemistry (miscellaneous),Ceramics and Composites

Reference112 articles.

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2. USNRC. Identification and Prioritization of the Technical Information Needs Affecting Potential Regulation of Extended Storage and Transportation of Spent Nuclear Fuel (United States Nuclear Regulatory Commission, 2014).

3. Hanson, B. et al. Gap Analysis to Support Extended Storage of Used Nuclear Fuel Rev. 0. (U. S. Department of Energy, FCRD-USED-2011-000136, 2012).

4. Yeom, H. et al. Cold spray deposition of 304L stainless steel to mitigate chloride-induced stress corrosion cracking in canisters for used nuclear fuel storage. J. Nucl. Mater. 538, 152254 (2020).

5. USNWTRB. Chloride-Induced Stress Corrosion Cracking Potential in Dry-Storage Canister For Spent Nuclear Fuel (U. S. Nuclear Waste Technical Review Board, 2017).

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