Abstract
The limiting Reactivity Initiated Accident (RIA) Failure thresholds for Zircaloy claddings are generally those related to pellet cladding mechanical interaction (PCMI) in heavily hydrided claddings. The introduction of coatings on the outer surface of Zircaloy cladding mitigates the hydrogen uptake issue and it is likely that this failure mechanism is not applicable to those cladding designs. As such the motivation for new failure thresholds related to high temperature swelling, rupture, and embrittlement mechanisms is described in this summary. Experiments to evaluate these thresholds in a static water capsule in the TREAT reactor at Idaho National Laboratory is then proposed. The experimental capability is described, and preliminary modeling results presented showing the viability of the system.
| Original language | English |
|---|---|
| Pages (from-to) | 603-606 |
| Number of pages | 4 |
| Journal | Transactions of the American Nuclear Society |
| Volume | 121 |
| DOIs | |
| State | Published - 2019 |
| Event | 2019 Transactions of the American Nuclear Society, ANS 2019 - Washington, United States Duration: Nov 17 2019 → Nov 21 2019 |
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