About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
|
Environmentally Assisted Cracking: Theory and Practice
|
Presentation Title |
CISCC Repair & Mitigation Strategies in Nuclear Waste Storage Canisters |
Author(s) |
Janelle P. Wharry, Antonio Ramirez, Frank Pfefferkorn, Kumar Sridharan, Indrajit Charit, Vijay K Vasudevan, Luke Brewer, Paul G Allison, Jonathan Tatman |
On-Site Speaker (Planned) |
Janelle P. Wharry |
Abstract Scope |
This talk captures the state-of-the-research of repair and mitigation of chloride-induced stress corrosion cracking (CISCC) in nuclear waste storage canisters. In the U.S., more than 86,000 metric tons of nuclear waste are stored in stainless steel canisters within concrete overpacks. But the CISCC susceptibility of canister vertical seam welds is a mounting concern in the nuclear industry. Herein we evaluate solid-state technologies for repair and mitigation of canister CISCC, including cold spray, friction stir joining/surfacing, and friction stir additive (MELD) manufacturing. These technologies have been evaluated in accelerated chloride environments (e.g., Fe3Cl, MgCl2) and in less aggressive saltwater brine. All technologies show promise for reducing pitting, increasing crack initiation time, and repairing existing CISCC. However, CISCC suppression mechanisms may lead to CISCC susceptibility elsewhere on the canister. The state of knowledge will be discussed in the context of the practical implications of deploying CISCC repair and mitigation technologies. |
Proceedings Inclusion? |
Planned: |
Keywords |
Environmental Effects, Nuclear Materials, Process Technology |