Uranium–molybdenum nuclear fuel plates behaviour under heavy ion irradiation: An X-ray diffraction analysis

Palancher, H.; Wieschalla, N.; Martin, Philippe; Tucoulou, R.; Sabathier, C.; Petry, W.; Bérar, J. F.; Valot, C.; Dubois, S.

doi:10.1016/j.jnucmat.2008.12.032

Cited by 31 publications

(27 citation statements)

References 17 publications

(28 reference statements)

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“…Finally screening tests to optimise the thermal treatment duration at 425 • C (and thus SiRDL characteristics) should be performed. This study could be carried out using smaller samples (miniplates) that are less expensive than full-size plates [43,44].…”

Section: Resultsmentioning

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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Section: Resultsmentioning

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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“…Of course one could say that if an amorphous phase, like UAl 4 , was also present, the μXRD may not have revealed its presence. A more recent study by most of these same experimenters 61 used the U-7Mo and U-10Mo in pure Al, irradiated with 80-MeV 127 I ions at less than 170°C, and performed a much more detailed XRD and μXRD analysis and obtained the same results. The UAl 3 phase was the only IL phase identified.…”

Section: Ion Irradiation -Il Phases Producedmentioning

confidence: 92%

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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“…Contrary to what is observed after in-pile experiments the IDL induced by ion irradiation is mainly composed of crystalline phases (i.e. UAl 3 ) [20]. Therefore improvements of the irradiation conditions have to be considered in order to obtain an amorphous IDL closer to in-pile tests.…”

Section: Introductionmentioning

confidence: 92%

“…It has been demonstrated that an IDL has developed in heavy ion irradiated fuel plates [18][19][20][21]. It is worth mentioning that no cU-Mo destabilization has been detected and that the IDL elemental composition is the same as in in-pile irradiated fuel plates [22].…”

Section: Introductionmentioning

confidence: 99%

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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Uranium–molybdenum nuclear fuel plates behaviour under heavy ion irradiation: An X-ray diffraction analysis

Cited by 31 publications

References 17 publications

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

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

Interaction Layer Characteristics in U-xMo Dispersion/Monolithic Fuels

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

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