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Evaluation Of SCC Susceptibility Of Steels Used In Nuclear Waste Storage Tanks In Caustic Simulants

Product Number: 51321-17012-SG
Author: B.C. Rollins; S. Chawla; K.J. Evans; K.M. Sherer; J. Gerst; N. Sridhar; J.A. Beavers; C. Girardot; T. Venetz
Publication Date: 2021
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$20.00
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Stress corrosion cracking (SCC) is a documented threat to the integrity of carbon steel radioactive waste storage tanks. An extensive amount of work has been carried out in caustic simulants of Hanford wastes containing between 6 and 12 M sodium hydroxide. Most of this historic work was performed at temperatures above 100°C, which is significantly warmer than current tank conditions. Current and future tank operations at Hanford need to consider the impact of caustic additions at temperatures below 75°C. A test program was designed to evaluate the SCC susceptibility risk in caustic simulants at temperatures below 75°C. Slow
strain rate (SSR) tests and fast and slow scan anodic polarization scans were used to evaluate the susceptibility of the carbon steel to SCC in various 10 M sodium hydroxide caustic environments.

Stress corrosion cracking (SCC) is a documented threat to the integrity of carbon steel radioactive waste storage tanks. An extensive amount of work has been carried out in caustic simulants of Hanford wastes containing between 6 and 12 M sodium hydroxide. Most of this historic work was performed at temperatures above 100°C, which is significantly warmer than current tank conditions. Current and future tank operations at Hanford need to consider the impact of caustic additions at temperatures below 75°C. A test program was designed to evaluate the SCC susceptibility risk in caustic simulants at temperatures below 75°C. Slow
strain rate (SSR) tests and fast and slow scan anodic polarization scans were used to evaluate the susceptibility of the carbon steel to SCC in various 10 M sodium hydroxide caustic environments.

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