BWR plants, stress corrosion cracking (SCC) in components such as the reactor core shroud and primary loop re-circulation (PLR) piping made of Lgrade stainless steel (SS) has been an issue since 2003.
Investigation on SCC in the core shroud has revealed the following,
- Nearly 3601 circumferential discrete cracks existed in the ring along the weld between the shroud shell and the ring. Most of the cracks were several mm away from the fusion line.
- Several radial cracks were found in the heat-affected zone (HAZ) of H4 weld, the highest fluence position in the shroud, some of which propagated into the weld metal
Since the reactor core shroud suffers from neutron irradiation, it would provide different SCC behaviors. Main factors for increasing crack growth rates seem to be the increased yield strength due to the cyclic weld heat input and the neutron irradiation effect.
Fig. 1. Reactor core shroud:
Fig. 2. Preparation procedure of the 316L H3 weld mock-up:
Fig. 3. Geometry of 0.5T-CT specimen made from the shroud mockups (Dimensions are in mm):
Fig. 4 Geometry of 1T-CT specimen made from the actually used shroud:
Fig. 5. Result of micro-vickers hardness measurement (H3):
Fig. 6. Result of micro-vickers hardness measurement (H4):
See this Experimental procedure at the following url,
http://www.4shared.com/file/153740839/ef18c0d/SCC_growth_behavior_of_BWR_core_shroud_materials.html
No comments:
Post a Comment
We appreciate your comments and feedbacks!