Abstract
Ongoing work is being performed to identify performance differences between Zircaloy and FeCrAl cladding in an LWR environment under accident conditions. Early results from this analysis, indicate that the burst temperatures of both cladding materials are generally similar. Figure 1 shows the maximum cladding temperature over the expected accident conditions, starting slightly before the onset of the accident conditions for both cladding types and the three fuel burnups. After cladding burst has occurred, the simulations are extended by considering a thermal-only solution capability implemented in the fuel performance code to demonstrate the effect of the cladding oxidation reaction at temperatures beyond burst.
| Original language | English |
|---|---|
| Pages (from-to) | 1523-1524 |
| Number of pages | 2 |
| Journal | Transactions of the American Nuclear Society |
| Volume | 118 |
| State | Published - 2018 |
| Externally published | Yes |
| Event | 2018 Transactions of the American Nuclear Society, ANS 2018 and Embedded Topical Meeting Nuclear Fuels and Structural Materials - Philadelphia, United States Duration: Jun 17 2018 → Jun 21 2018 |