scholarly journals STRESS CORROSION CRACKING SUSCEPTIBILITY OF HIGH LEVEL WASTE TANKS DURING SLUDGE MASS REDUCTION

2007 ◽  
Author(s):  
K Subramanian
Keyword(s):  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Corrosion Cracking ◽  
High Level Waste ◽  
Mass Reduction ◽  
Waste Tanks ◽  
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 Potential for Stress Corrosion Cracking of A537 Carbon Steel Nuclear Waste Tanks Containing Highly Caustic Solutions

2010 ◽  
Author(s):  
Poh-Sang Lam ◽  
Craig S. Stripling ◽  
Donald L. Fisher ◽  
James B. Elder
Keyword(s):  
Carbon Steel ◽  
Stress Corrosion ◽  
Nuclear Waste ◽  
Stress Corrosion Cracking ◽  
Corrosion Cracking ◽  
Welding Residual Stress ◽  
Caustic Solution ◽  
Experimental Program ◽  
General Corrosion ◽  
Waste Tanks

The evaporator recycle streams of nuclear waste tanks may contain waste in a chemistry and temperature regime that exceeds the current corrosion control program, which imposes temperature limits to mitigate caustic stress corrosion cracking (CSCC). A review of the recent service history found that two of these A537 carbon steel tanks were operated in highly concentrated hydroxide solution at high temperature. Visual inspections, experimental testing, and a review of the tank service history have shown that CSCC has occurred in uncooled/un-stress relieved tanks of similar construction. Therefore, it appears that the efficacy of stress relief of welding residual stress is the primary corrosion-limiting mechanism. The objective of this experimental program is to test A537 carbon steel small scale welded U-bend specimens and large welded plates (30.48 × 30.38 × 2.54 cm) in a caustic solution with upper bound chemistry (12 M hydroxide and 1 M each of nitrate, nitrite, and aluminate) and temperature (125 °C). These conditions simulate worst-case situations in these nuclear waste tanks. Both as-welded and stress-relieved specimens have been tested. No evidence of stress corrosion cracking was found in the U-bend specimens after 21 days of testing. The large plate test was completed after 12 weeks of immersion in a similar solution at 125 °C except that the aluminate concentration was reduced to 0.3 M. Visual inspection of the plate revealed that stress corrosion cracking had not initiated from the machined crack tips in the weld or in the heat affected zone. NDE ultrasonic testing also confirmed subsurface cracking did not occur. Based on these results, it can be concluded that the environmental condition of these tests was unable to develop stress corrosion cracking within the test periods for the small welded U-bends and for the large plates, which were welded with an identical procedure as used in the construction of the actual nuclear waste tanks in the 1960s. The absence of evidence of stress corrosion cracking and general corrosion in the laboratory-scaled specimens indicate that this type of nuclear waste tank is not susceptible to highly caustic solutions up to 12 M hydroxide at 125 °C when sufficient nitrite inhibitor is present.

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
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