2007 International RERTR Meeting

Abstracts and Available Papers Presented at the Meeting

Nuclear Fuel Development Based on UMo Alloys Under Irradiation Evaluation of LEU U₃Si₂ - 4.8 gU/cm³ Test Fuel

L. Olivares, J. Marin, M. Barrera, G. Torres and J. Lisboa
Nuclear Materials Deptartment
Chilean Commission for Nuclear Energy - CCHEN
95  Amunategui St., Santiago, Chile

ABSTRACT

Latest irradiation reports on UMo dispersion fuel demand different solutions in order to stabilize an undesirable interaction layer zone produced by chemical reactions with the standard Al matrix. Among the different solutions, this paper addresses the evaluation of the addition of Si to the Al matrix and/or small amount of tetravalent elements (Si, Zr, and Ti) to the fuel. The results of out-of-pile swelling tests applied to dispersion mini plates made of these modified constituents and interaction tests of interdiffusion couples are discussed. These results show that the volume changes are directly related with the uranium density. The unmodified UMo/Al system exhibited swelling levels almost three times higher than those achieved with U₃Si₂, however for the system UMo/AlSi mix, these undesired behavior was reduced to values equivalent or slightly  lower than U₃Si₂. Finally, details and specifications of a LEU U₃Si₂ 4,8 gU/cm³ test fuel element, fabricated for under irradiation evaluation and design validation purposes at the RECH-1 research reactor, are reported in this paper. The planned follow-up program and initial irradiation results showing an appropriate performance that allows reaching the expected ²³⁵U burn up level, slightly over 50% are detailed and discussed.

 

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