| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 11001152 | Nuclear Engineering and Design | 2018 | 14 Pages |
Abstract
The CHF and the Departure from Nucleate Boiling Ratio (DNBR) were calculated using the Consortium for Advanced Simulation of Light Water Reactors (CASL) subchannel code COBRA-TF (CTF) for a one-eighth model of a 17â¯Ãâ¯17 Pressurized Water Reactor (PWR) fuel assembly. The inlet conditions are consistent with typical PWR values except for the power, which was set 50% higher than is typical to represent possible accident conditions more accurately. The calculated distributions for the CHF and DNBR for oxidized FeCrAl showed significantly higher values throughout the fuel assembly octant compared to as machined Zirc-4 and as machined FeCrAl. These preliminary results show that oxidized FeCrAl may be able to withstand the proposed accident conditions without leading to a boiling crisis.
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Authors
Amir F. Ali, Jacob P. Gorton, Nicholas R. Brown, Kurt A. Terrani, Colby B. Jensen, Youho Lee, Edward D. Blandford,