| About this Abstract |
| Meeting |
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Symposium
|
Materials in Nuclear Energy Systems (MiNES) 2021
|
| Presentation Title |
Structural Materials Testing for the Westinghouse Lead Fast Reactor |
| Author(s) |
Mike Ickes, Paolo Ferroni |
| On-Site Speaker (Planned) |
Mike Ickes |
| Abstract Scope |
Westinghouse continues to develop the Lead Fast Reactor (LFR) as its Generation IV reactor concept, with the mission to provide safe, sustainable, and especially economical carbon-free electricity generation to global market. The Westinghouse LFR is a 950 MWt (~460 MWe) pool-type reactor with compact in-vessel heat exchangers and no intermediate heat transport system.
The operation of an LFR at temperatures greater than approximately 500°C is challenged by liquid lead corrosion of structural materials. Recognizing that some key components such as the reactor vessel and the primary pumps will operate at cold leg temperature (~400°C), some others will operate at higher temperatures. Investigations into materials integrity under reactor operating conditions to allow operation at higher temperature are therefore an important aspect of LFR development to maximize the economic performance of the LFR. Some key aspects and select results from the R&D campaign supporting the Westinghouse LFR will be presented and discussed. |
| Proceedings Inclusion? |
Undecided |