| About this Abstract |
| Meeting |
2019 TMS Annual Meeting & Exhibition
|
| Symposium
|
Coatings and Surface Engineering for Environmental Protection
|
| Presentation Title |
Protective Coating for Nuclear Fuel Claddings |
| Author(s) |
Kiran Nimishakavi, Jeremy Bischoff, John Strumpell |
| On-Site Speaker (Planned) |
John Strumpell |
| Abstract Scope |
Zirconium based alloys are essential structural materials used in the core of the nuclear reactor, due to the low absorption of neutrons and high corrosion resistance. However, during severe accident conditions zirconium reacts with steam to release large amounts of hydrogen and heat, which further increases the severity of an accident. The most effective way to prevent such accidents is to develop advanced alloys which show superior resistance to steam oxidation, thereby reducing the total heat generation. Framatome with added support from Department of Energy (DOE) is actively working on coated cladding technology which demonstrates enhanced performance in both normal and accidental conditions and could potentially be implemented with minimal changes to the current fuel designs. This presentation will provide an overview of the development status of Framatome’s Cr-coated cladding and highlights numerous benefits this advanced fuel concept offer to nuclear industry, including those beyond the increased safety margin. |
| Proceedings Inclusion? |
Planned: Supplemental Proceedings volume |