Oxidation behaviour of PM-C26M FeCrAl alloy in low-temperature steam 400 – 900 °C
Iron-chromium-aluminum (FeCrAl) alloys are the primary candidate for serving as an accident tolerant fuel cladding, replacing zirconium (Zr)-based cladding. This preference stems from the high corrosion resistance under both operating and accident conditions in light water reactors (LWRs). To succes...
| Published in: | Nuclear Materials and Energy |
|---|---|
| Main Authors: | , , , , |
| Format: | Article |
| Language: | English |
| Published: |
Elsevier
2025-06-01
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| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S235217912500095X |
