Full-length U–xPu–10Zr (x=0, 8, 19wt.%) fast reactor fuel test in FFTF

• Published in: Journal of nuclear materials 2012-08, Vol.427 (1-3), p.46-57
• Main Authors: Porter, D.L., Tsai, Hanchung
• Format: Article
• Language: English
• Subjects: Applied sciences; Cladding; Controled nuclear fusion plants; Electron probes; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Fission nuclear power plants; Fission products; Fuels; Gas composition; Installations for energy generation and conversion: thermal and electrical energy; Nuclear engineering; Nuclear fuels; Nuclear power generation; Nuclear reactor components; Nuclear reactors; Position (location); Rare earth metals
• ISSN: 0022-3115; 1873-4820
• DOI: 10.1016/j.jnucmat.2012.03.047

The Integral Fast Reactor-1 (IFR-1) experiment performed in the Fast Flux Test Facility (FFTF) was the only U–Pu–10Zr (Pu-0, 8 and 19wt.%) metallic fast reactor test with commercial-length (91.4-cm active fuel-column length) conducted to date. With few remaining test reactors, there is little opportunity for performing another test with a long active fuel column. The assembly was irradiated to the goal burnup of 10at.%. The beginning-of-life (BOL) peak cladding temperature of the hottest pin was 608°C, cooling to 522°C at end-of-life (EOL). Selected fuel pins were examined non-destructively using neutron radiography, precision axial gamma scanning, and both laser and spiral contact cladding profilometry. Destructive exams included plenum gas pressure, volume, and gas composition determinations on a number of pins followed by optical metallography, electron probe microanalysis (EPMA), and alpha and beta–gamma autoradiography on a single U–19Pu–10Zr pin. The post-irradiation examinations (PIEs) showed very few differences compared to the short-pin (34.3-cm fuel column) testing performed on fuels of similar composition in Experimental Breeder Reactor-II (EBR-II). The fuel column grew axially slightly less than observed in the short pins, but with the same pattern of decreasing growth with increasing Pu content. There was a difference in the fuel–cladding chemical interaction (FCCI) in that the maximum cladding penetration by interdiffusion with fuel/fission products did not occur at the top of the fuel column where the cladding temperature is highest, as observed in EBR-II tests. Instead, the more exaggerated fission-rate profile of the FFTF pins resulted in a peak FCCI at ∼0.7 X/L axial location along the fuel column. This resulted from a higher production of rare-earth fission products at this location and a higher ΔT between fuel center and cladding than at core center, together providing more rare earths at the cladding and more FCCI. This behavior could actually help extend the life of a fuel pin in a “long pin” reactor design to a higher peak fuel burnup.