Title of article :
Performance of FCCI barrier foils for U–Zr–X metallic fuel
Author/Authors :
Ryu، نويسنده , , Ho Jin and Lee، نويسنده , , Byoung Oon and Oh، نويسنده , , Seok Jin and Kim، نويسنده , , Jun Hwan and Lee، نويسنده , , Chan Bock، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2009
Pages :
7
From page :
206
To page :
212
Abstract :
Diffusion couple tests of U–Zr or U–Zr–Ce alloys vs. ferritic martensitic steels such as HT9 or T91 were carried out in order to evaluate the performance of the diffusion barrier candidates. Elemental metal foils of Zr, Nb, Ti, Mo, Ta, V and Cr were very effective in inhibiting interdiffusion between these fuels and steels. Eutectic melting between the fuels and steels was not observed in any of the diffusion couples using these diffusion barrier foils at annealing temperatures up to 800 °C. Among the metallic foils evaluated in this study, V and Cr exhibited the most promising performances as a diffusion barrier material for eliminating the fuel cladding chemical interaction problem. However, Zr, Nb and Ti showed an active interaction with the fuel mainly due to the large U solubility.
Journal title :
Journal of Nuclear Materials
Serial Year :
2009
Journal title :
Journal of Nuclear Materials
Record number :
1365013
Link To Document :
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