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.
|Title of host publication||TRANSACTIONS- AMERICAN NUCLEAR SOCIETY|
|Place of Publication||United States|
|State||Published - 1 Apr 2012|
|Event||2012 American Nuclear Society annual meeting - Chicago|
Duration: 23 Jun 2012 → 29 Jun 2012
|Conference||2012 American Nuclear Society annual meeting|
|Period||2012-06-23 → 2012-06-29|