Microstructure of the irradiated U3Si2/Al silicide dispersion fuel

Gan, Jian; Keiser, Dennis D.; Miller, Brandon; Jue, Jan‐Fong; Robinson, Adam; Madden, James W.; Medvedev, Pavel; Wachs, D. M.

doi:10.1016/j.jnucmat.2011.07.030

Cited by 28 publications

(16 citation statements)

References 13 publications

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“…The most important information from the characterization of the high flux U-7Mo/Al-5Si sample is the capturing of the GBS collapsing at the given fission density of 5.210 21 fissions/cm 3 it is believed that SFP precipitates out first, and then preferentially absorbs fission gas atoms and forms large bubbles around the SFP precipitates. At GBS collapse significant fraction of the U-Mo matrix turns to amorphous and subsequently the SFP mobility increases and promotes SFP precipitation.…”

Section: Discussionmentioning

confidence: 99%

Microstructural characterization of irradiated U–7Mo/Al–5Si dispersion fuel to high fission density

Gan

Miller

Keiser

et al. 2014

Journal of Nuclear Materials

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The fuel development program for research and test reactors calls for improved knowledge on the effect of microstructure on fuel performance in reactors. This paper summarizes the recent TEM microstructural characterization of an irradiated U-7Mo/Al-5Si dispersion fuel plate (R3R050) in the Advanced Test Reactor (ATR) at Idaho National Laboratory (INL) to 5.2×10 21 fissions/cm 3. While a large fraction of the fuel grains is decorated with large bubbles, there is no evidence showing interlinking of these bubbles at the specified fission density. The attachment of solid fission product precipitates to the bubbles is likely the result of fission product diffusion into these bubbles. The process of fission gas bubble superlattice collapse appears through bubble coalescence. The results are compared with the previous TEM work on the dispersion fuels irradiated to lower fission density from the same fuel plate. Acknowledgment is given to the INL Hot Fuel Examination Facility staff for producing the punching sample from fuel plate R3R050.

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Section: Discussionmentioning

confidence: 99%

Microstructural characterization of irradiated U–7Mo/Al–5Si dispersion fuel to high fission density

Gan

Miller

Keiser

et al. 2014

Journal of Nuclear Materials

Self Cite

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show abstract

“…In the U 3 Si 2 fuel development, a FMI layer formed between the U 3 Si 2 fuel kernel and Al matrix. This layer was shown to be stable at high burnups (23).…”

Section: Rertr-1 and Rertr-2 Testsmentioning

confidence: 93%

“…In addition, Si was added to the Al-matrix to try to help stabilize the growth of the FMI layer and control the breakaway swelling. This was done to try to form the FMI phase, U(Al,Si) 3 , the phases found in FMI layer in U 3 Si 2 /Al dispersion fuel (23). This phase has been shown to stable be at high burnups.…”

Section: Rertr-6 Testmentioning

confidence: 99%

“…The goal of Si addition to the FMI layer is to drive the layer towards the U(Al,Si) 3 phase. U(Al,Si) 3 is present in the FMI layer in the U 3 Si 2 dispersion fuels that have been shown to be stable at high burnups (23).…”

Section: Al-matrix Modificationmentioning

confidence: 99%

“…Specifically, work at the INL on a U 3 Si 2 /Al silicide dispersion fuel shows that the U(Al,Si) 3 FMI layer is amorphous in character after irradiation (23). Additionally, the FMI layer formed in UAl x /Al dispersion is amorphous (74).…”

Section: 13: Why the Fmi Layer Is Amorphousmentioning

confidence: 99%

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