Abstract
In summary, two complementary techniques were used to characterize phases formed as a result of interdiffusion between U-Pu-Zr metal fuel and cladding and fission gas bubbles produced in U-Mo fuel upon irradiation. Understanding in-reactor degradation behavior of these materials is critical to advancing nuclear energy technology.
| Original language | English |
|---|---|
| Pages (from-to) | 1251-1252 |
| Number of pages | 2 |
| Journal | Transactions of the American Nuclear Society |
| Volume | 114 |
| Issue number | 1 |
| State | Published - 2016 |
| Event | 2016 Transactions of the American Nuclear Society Annual Meeting, ANS 2016 - New Orleans, United States Duration: 12 Jun 2016 → 16 Jun 2016 |