Metallography and fuel cladding chemical interaction in fast flux test facility irradiated metallic U-10Zr MFF-3 and MFF-5 fuel pins

JOURNAL OF NUCLEAR MATERIALS

卷:473

Article

Carmack, W. J.¹  Chichester, H. M.¹  Porter, D. L.¹  Wootan, D. W.² 

[1] Idaho Natl Lab, POB 1625, Idaho Falls, ID 83415 USA

[2] Pacific NW Natl Lab, POB 999, Richland, WA 99354 USA

关键词: Metallography;    Fuel cladding chemical interaction;    Irradiated fuel pins;    MFF;    FFTF;   

DOI  :  10.1016/j.jnucmat.2016.02.019

来源: Elsevier

【 摘 要 】

The Mechanistic Fuel Failure (MFF) series of metal fuel irradiations conducted in the Fast Flux Test Facility (FFTF) provides an important comparison between data generated in the Experimental Breeder Reactor (EBR-II) and that expected in a larger-scale fast reactor. The MFF fuel operated with a peak cladding temperature at the top of the fuel column, but developed peak burnup at the centerline of the core. This places the peak fuel temperature midway between the core center and the top of fuel, lower in the fuel column than in EBR-II experiments. Data from the MFF-3 and MFF-5 assemblies are most comparable to the data obtained from the EBR-II X447 experiment. The two X447 pin breaches were strongly influenced by fuel/cladding chemical interaction (FCCI) at the top of the fuel column. Post irradiation examination data from MFF-3 and MFF-5 are presented and compared to historical EBR-II data. (C) 2016 Elsevier B.V. All rights reserved.

【 授权许可】

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