Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Performance of FBTR mixed carbide fuel

Abstract

Mixed carbide fuel of 70% PuC content is being used as driver fuel in the Fast Breeder Test Reactor (FBTR) for the first time in the world. When it was first proposed for FBTR small core, its performance potential had to be assessed based upon extrapolated data. High Pu content of the fuel reduces the thermal conductivity and melting point. Also, small diameter of FBTR fuel results in high heat flux at fuel-clad gap. A conservative initial estimate limited the linear power to 250 W/cm and the burnup to 25,000 MWd/t. Subsequently, detailed analyses were performed with the use of measured as well as data from literature. Based on this, the linear power has been upgraded to 320 W/cm. Also analyses indicate that the fuel is capable of sustaining a peak burnup of 50,000 MWd/t. Recently, the central fuel subassembly was unloaded for post irradiation examination (PIE) after the initial target burnup of 25,000 MWd/t. Preliminary results from PIE indicate that the analysis is well supported by the results.

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Reference:

Influence of high dose irradiation on core structural and fuel materials in advanced reactors. Technical committee meeting, Obninsk (Russian Federation), 16-19 Jun 1997

International Atomic Energy Agency, Vienna (Austria)

IAEA-TECDOC--1039, pp:47-56