| About this Abstract |
| Meeting |
MS&T23: Materials Science & Technology
|
| Symposium
|
Progressive Solutions to Improve Corrosion Resistance of Nuclear Waste Storage Materials
|
| Presentation Title |
Chloride-induced Stress Corrosion Crack in Spent Nuclear Fuel Canisters: Understanding and Mitigating |
| Author(s) |
Haozheng Qu, Janelle P. Wharry |
| On-Site Speaker (Planned) |
Haozheng Qu |
| Abstract Scope |
This talk captures the state-of-the-research of fundamental understanding and repair techniques of chloride-induced stress corrosion cracking (CISCC) in nuclear waste storage canisters. In the U.S. only, more than 86,000 metric tons of nuclear waste are stored in over 3,300 stainless steel canisters and CISCC threat of the weld regions is a mounting concern in the nuclear industry. Here, we review the recent advancement in the fundamental understanding of CISCC mechanism discovered with the state-of-art characterization techniques. The crystallographic and micromechanical perspectives of transgranular CISCC will be assessed, including the strain mismatch across grain pairs along crack path, correlation between hardness and CISCC susceptibility, phase transformation etc. We will evaluate recent development and application of cold spray coating as a solid-state repair and mitigation method for canister CISCC. The state of knowledge for cold spray will be discussed in the context of fundamental mechanism and practical implication of CISCC resistance improvement. |