Fission Gas Bubbles Characterisation in Irradiated UO2 Fuel by SEM, EPMA and SIMS

Lamontagne, J.; Desgranges, Lionel; Valot, C.; Noirot, J.; Blay, Thierry; Roure, I.; Pasquet, B.

doi:10.1007/s00604-006-0540-y

Cited by 27 publications

(10 citation statements)

References 8 publications

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“…As a consequence, such measurements underestimate Xe concentration especially when they are located in large bubbles. For a more reliable quantification, it has been suggested to combine for example these characterisations with secondary ion mass spectrometry (SIMS) which do not suffer from this specific limitation [40].…”

Section: Epmamentioning

confidence: 99%

Annealing tests of in-pile irradiated oxide coated U–Mo/Al–Si dispersed nuclear fuel

Zweifel¹,

Valot²,

Pontillon³

et al. 2014

Journal of Nuclear Materials

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is an open access repository that collects the work of Arts et Métiers ParisTech researchers and makes it freely available over the web where possible. a b s t r a c t U-Mo/Al based nuclear fuels have been worldwide considered as a promising high density fuel for the conversion of high flux research reactors from highly enriched uranium to lower enrichment. In this paper, we present the annealing test up to 1800 °C of in-pile irradiated U-Mo/Al-Si fuel plate samples. More than 70% of the fission gases (FGs) are released during two major FG release peaks around 500 °C and 670 °C. Additional characterisations of the samples by XRD, EPMA and SEM suggest that up to 500 °C FGs are released from IDL/matrix interfaces. The second peak at 670 °C representing the main release of FGs originates from the interaction between U-Mo and matrix in the vicinity of the cladding.

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Section: Epmamentioning

confidence: 99%

Annealing tests of in-pile irradiated oxide coated U–Mo/Al–Si dispersed nuclear fuel

Zweifel¹,

Valot²,

Pontillon³

et al. 2014

Journal of Nuclear Materials

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show abstract

“…Finally, studies [5][6][7] have provided further information especially with an assessment of the quantity of fission gas in a single bubble in the rim area and the confirmation of low fission gas release from this area by secondary ion mass spectrometer (SIMS).…”

Section: Introductionmentioning

confidence: 99%

Detailed characterisations of high burn-up structures in oxide fuels

Noirot

Desgranges

Lamontagne

2008

Journal of Nuclear Materials

150

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“…It is now possible to characterise irradiated samples with the SIMS, and xenon has been measured on irradiated UO 2 fuel [3,11]. The xenon filling the bubbles is detected as peaks on the xenon signal measured during a depth profile [12].…”

Section: Introductionmentioning

confidence: 99%

A method for the quantification of total xenon concentration in irradiated nuclear fuel with SIMS and EPMA

Desgranges¹,

Valot²,

Pasquet³

et al. 2008

Nuclear Instruments and Methods in Physics Research Section B:

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Fission Gas Bubbles Characterisation in Irradiated UO2 Fuel by SEM, EPMA and SIMS

Cited by 27 publications

References 8 publications

Annealing tests of in-pile irradiated oxide coated U–Mo/Al–Si dispersed nuclear fuel

Annealing tests of in-pile irradiated oxide coated U–Mo/Al–Si dispersed nuclear fuel

Detailed characterisations of high burn-up structures in oxide fuels

A method for the quantification of total xenon concentration in irradiated nuclear fuel with SIMS and EPMA

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