Fuel performance assessment of the lead-bismuth cooled MYRRHA reactor
Research output: Contribution to report/book/conference proceedings › In-proceedings paper › peer-review
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Abstract
The assessment of the (safety-related) performance of the driver fuel rods of the reactor is of key importance to the licensing process of MYRRHA, which is currently in its “pre-licensing” phase. Although the fuel rod design is largely based on past (sodium) fast reactor experience, the use of LBE as the coolant requires a thorough re-evaluation of the fuel design for specific MYRRHA conditions. This paper presents preliminary results.
Details
| Original language | English |
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| Title of host publication | TRANSACTIONS- AMERICAN NUCLEAR SOCIETY |
| Place of Publication | United States |
| Pages | 1201-1204 |
| Publication status | Published - 1 Apr 2012 |
| Event | 2012 American Nuclear Society annual meeting - Chicago, United States Duration: 23 Jun 2012 → 29 Jun 2012 |
Conference
| Conference | 2012 American Nuclear Society annual meeting |
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| Country/Territory | United States |
| City | Chicago |
| Period | 2012-06-23 → 2012-06-29 |
Keywords
- MYRRHA, fuel performance
ID: 246776