scholarly journals Stress Corrosion Cracking Model for High Level Radioactive-Waste Packages

2004 ◽  
Author(s):  
P. Andresen ◽  
G. Gordon ◽  
S. Lu
Keyword(s):  
Radioactive Waste ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Corrosion Cracking ◽  
High Level Radioactive Waste ◽  
High Level

Stress corrosion cracking susceptibility of P285NH and API 5L X65 steel grades in the high‐level radioactive waste repository cell concept

2020 ◽  
Vol 72 (1-2) ◽  
pp. 154-165
Author(s):  
Nicolas Bulidon ◽  
Valérie Deydier ◽  
Frederic Bumbieler ◽  
Claude Duret‐Thual ◽  
Christophe Mendibide ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Corrosion Cracking ◽  
High Level Radioactive Waste ◽  
Steel Grades ◽  
X65 Steel ◽  
Waste Repository ◽  
Api 5L X65 Steel ◽  
High Level

An Approach to Model Abstraction of Stress Corrosion Cracking Damage in Management of Spent Nuclear Fuel and High-Level Waste

2013 ◽  
Author(s):  
Tae M. Ahn
Keyword(s):  
Crack Propagation ◽  
Stress Corrosion ◽  
Nuclear Fuel ◽  
Stress Corrosion Cracking ◽  
Spent Nuclear Fuel ◽  
Corrosion Cracking ◽  
Propagation Model ◽  
High Level Waste ◽  
Multiple Cracks ◽  
High Level

This paper presents an approach to assess stress corrosion cracking (SCC) damage of a canister for use in confinement management (extended dry storage or geological disposal) of radionuclides from spent nuclear fuel and high-level (radioactive) waste. Localized corrosion, mainly in pitting form and fabrication flaws, were analyzed as a possible precursor to SCC using field/laboratory data. This paper assesses single crack propagation over long time periods and estimates the potential maximum opening area resulting from multiple cracks. This crack propagation model was developed by the Sandia National Laboratories (SNL) for disposal under seismic conditions, and it appears to be conservative with respect to radionuclide releases through the opening area. The SNL model could be applied to the weld and various metals for both management applications. The conservative SNL approach could be used to estimate consequences of radionuclides dispersals, if a canister failed as the confinement barrier.

scholarly journals Control of Stress Corrosion Cracking in Storage Tanks Containing Radioactive Waste

1979 ◽  
Vol 44 (2) ◽  
pp. 297-306 ◽  
Author(s):  
R. S. Ondrejcin ◽  
S. P. Rideout ◽  
J. A. Donovan
Keyword(s):  
Radioactive Waste ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Corrosion Cracking ◽  
Storage Tanks

Structural Impact Assessment of Flaws Detected During Ultrasonic Examination of a Radioactive Waste Tank

2003 ◽  
Author(s):  
B. J. Wiersma ◽  
J. B. Elder
Keyword(s):  
Radioactive Waste ◽  
Residual Stresses ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Structural Integrity ◽  
Corrosion Damage ◽  
Corrosion Cracking ◽  
Crack Behavior ◽  
The Impact ◽  
Vapor Space

Ultrasonic (UT) inspection of an underground storage tank containing radioactive waste was conducted at the Savannah River Site (SRS). Ten cracks were identified during this examination. A critical review of the information describing stress corrosion crack behavior for the SRS waste tanks, as well as a summary review of the service history this tank, was performed. Each crack was then evaluated for service exposure history, consistency of the crack behavior with the current understanding of stress corrosion cracking, and present and future impact to the structural integrity of the tank. In all cases, the crack behavior was determined to be consistent with the previous understanding of stress corrosion cracking in the SRS waste tank environment. The length of the cracks was limited due to the short-range nature of the residual stresses near seam, repair and attachment welds. In many cases the cracks were associated with exposure to fresh waste from the SRS canyons as previously observed. However, cases in which the crack was observed to go through-wall while located in the vapor space above the waste were also observed. The time of initiation and propagation rate of these cracks is unknown. A re-examination of these cracks will determine whether these cracks are continuing to grow while in the vapor space. The impact of these cracks on the future service of this tank was also assessed. A bounding loading condition due waste removal of the sludge at the bottom of Tank 15 was considered for this analysis. The analysis showed that the combination of hydrostatic and weld residual stresses do not drive any of the cracks identified during the UT inspection to instability. For all cracks the instability length was more than 10 times the actual flaw length. The re-examination of this tank is scheduled for 2007. This examination would provide information to determine whether any additional detectable degradation is occurring and to supplement the basis for specification of conditions that are non-aggressive to tank corrosion damage for similar tanks at SRS.

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