FY21 Status Report: Probabilistic SCC Model for SNF Dry Storage Canisters

Technical Report · Fri Jul 30 00:00:00 EDT 2021

DOI:https://doi.org/10.2172/1822281· OSTI ID:1822281

Porter, Nathan W. ^[1]; Brooks, Dusty ^[2]; Bryan, Charles ^[2]; Katona, Ryan ^[2]; Schaller, Rebecca ^[2]

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1. Sandia National Laboratories (SNL), Albuquerque, NM, and Livermore, CA (United States)
2. Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

Stress corrosion cracking (SCC) is an important failure degradation mechanism for storage of spent nuclear fuel. Since 2014, Sandia National Laboratories has been developing a probabilistic methodology for predicting SCC. The model is intended to provide qualitative assessment of data needs, model sensitivities, and future model development. In fiscal year 2021, improvement of the SCC model focused on the salt deposition, maximum pit size, and crack growth rate models.

• Research Organization: Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: NA0003525
• OSTI ID: 1822281
• Report Number(s): SAND2021-9213R; 700148
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES