Microstructure of RERTR DU-alloys irradiated with krypton ions up to 100dpa

Gan, Jian; Keiser, Dennis D.; Miller, Brandon; Wachs, D. M.; Allen, Todd R.; Kirk, Marquis A.; Rest, J.

doi:10.1016/j.jnucmat.2011.01.121

Cited by 24 publications

(16 citation statements)

References 19 publications

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“…This work confirms that heavy ion irradiation is a unique method to study some modifications induced by in-pile irradiation in UMo/Al nuclear fuels. This conclusion is on-line with the recent investigations of UMoAlSi intermetallics amorphization under a 3 MeV Kr ion beam [45].…”

Section: Discussionsupporting

confidence: 92%

Evidence of amorphous interdiffusion layer in heavy ion irradiated U–8wt%Mo/Al interfaces

Chiang

Zweifel

Palancher

et al. 2013

Journal of Nuclear Materials

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Section: Discussionsupporting

confidence: 92%

Evidence of amorphous interdiffusion layer in heavy ion irradiated U–8wt%Mo/Al interfaces

Chiang

Zweifel

Palancher

et al. 2013

Journal of Nuclear Materials

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“…First a better estimation of SiRDL thicknesses would be obtained. Second a definitive conclusion on the presence of phases with poor in-pile performances (like U 6 Mo 4 Al 43 or UAl 4 ) could be proposed [39]. Finally from a methodological point of view, such a work would be interesting for defining the limits of these macroscopic and volume measurements in describing the slight evolutions of SiRDL composition with manufacturing conditions.…”

Section: Possible Complementary Measurementsmentioning

confidence: 99%

Quantitative crystallographic analysis of as-fabricated full size U–Mo/Al(Si) nuclear fuel plates

Palancher

Bonnin

Honkimäki

et al. 2012

Journal of Alloys and Compounds

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“…The study by Miller et al 60 irradiating with energetic ions and protons and discussed in more detail in the next section of this article, would support the last observation because crystalline phases were not made amorphous by 200°C proton irradiation. A follow-up study by Gan et al, 81 discussed in more detail in the next section, also produced consistent results.…”

Section: Ion Irradiation -Il Phases Producedmentioning

confidence: 53%

“…81 They had identified the phases UAl 4 , U(Si,Al) 3 , (U,Mo)(Si,Al) 3 , UMo 2 Al 20 , and U 6 Mo 4 Al 43 in the as-cast alloys. This study provided a more detailed evaluation of the conditions under which these phases became amorphous, although only one temperature was used.…”

Section: Effect Of Irradiation On Ilmentioning

confidence: 99%

Interaction Layer Characteristics in U-xMo Dispersion/Monolithic Fuels

Porter¹

2010

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SUMMARYPublished data concerning the interaction layer (IL) formed between U-xMo fuel alloy and aluminum (Al)-based matrix or cladding materials was reviewed, including the effects of silicon (Si) content in the matrix/cladding, molybdenum (Mo) content in the fuel, pre-irradiation thermal treatments, irradiation, and test temperature. The review revealed that tests conducted in the laboratory produce results different from those conducted in an irradiation environment. However, the laboratory testing relates well to thermal treatments performed prior to irradiation and helps in understanding the effects that these pre-irradiation treatments have on in-reactor performance. A small, Si-enriched IL, formed during a step in the fabrication process, seems to be stable during irradiation, helping to prevent the rapid growth of an irradiation-induced IL. Moreover, the Si-enriched IL seems to be important in delaying the onset of rapid growth of fission gas bubbles.Conclusions from irradiated fuels data have been repeated many times in the literature review. However, as related to the "Desired Characteristics of the IL" mentioned near the beginning of this report, several more conclusions can be drawn:1. An IL with phases akin to UAl 3 is desired for optimum fuel performance, but at low temperatures, and especially in an irradiation atmosphere, the desired (Al+Si)/(U+Mo) ratio of three is difficult to produce. When the fuel operating temperature is low, it is important to create a pre-irradiation IL enriched in Si. This pre-formed IL is relatively stable, performs well in terms of swelling resistance, and prevents rapid IL growth during irradiation. Fabrication-related heat treatments should be limited in order to maintain a thin, Si-enriched layer containing potentially beneficial phases.2. At higher operating temperatures (>150-170°C), IL formation in reactor may not be so dependent on pre-irradiation IL formation, especially at high burnup; a pre-fabricated IL seems to be less stable at high burnup and high operating temperature. Moreover, the (Al+SI)/(U+Mo) ratio of three occurs more often at higher temperature. For these two reasons, it is important at high operating temperature to also have a matrix with significant Si content to create an IL in-reactor with the right characteristics.3. Out-of-reactor testing seems to indicate that Si in the matrix material is required in some concentration (2%, 5%, ?) to provide for a thin, Si-enriched IL formed before irradiation of a fuel plate. It ensures that the IL contains beneficial phases or prevents formation of some known to promote poor fuel performance. Significant progress has been made in determining the desired characteristics of the IL.4. The use of a fuel with stable gamma phase appears to allow more predictable performance regarding both a beneficial pre-irradiation layer and the fuel performance (low swelling) to high burnup. Destabilization of the gamma phase may create problems with IL breakaway growth.5. A theory whereby prevention of the U 6 Mo 4 Al 43 comp...

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Microstructure of RERTR DU-alloys irradiated with krypton ions up to 100dpa

Cited by 24 publications

References 19 publications

Evidence of amorphous interdiffusion layer in heavy ion irradiated U–8wt%Mo/Al interfaces

Evidence of amorphous interdiffusion layer in heavy ion irradiated U–8wt%Mo/Al interfaces

Quantitative crystallographic analysis of as-fabricated full size U–Mo/Al(Si) nuclear fuel plates

Interaction Layer Characteristics in U-xMo Dispersion/Monolithic Fuels

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