Determining the americium transmutation rate and fission rate by post-irradiation examination within the scope of the ECRIX-H experiment

Lamontagne, J.; Pontillon, Yves; Esbelin, E.; Béjaoui, S.; Pasquet, B.; Bourdot, P.; Bonnerot, J.M.

doi:10.1016/j.jnucmat.2013.05.057

Cited by 8 publications

(6 citation statements)

References 32 publications

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“…Thus, one major goal of U-Mo/Al development is to understand this fission gas behaviour. The approach chosen for this work consists in combining in situ monitoring of FG release during thermal treatments with destructive examinations of the annealed samples [10]. This methodology is aimed at defining the initial location of fission gas inside the fuel material and understanding their behaviour.…”

Section: Introductionmentioning

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: Introductionmentioning

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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“…Second, specifically for the quantification of Am, a missing reference for Am can be replaced by measuring the Am in-growth in the PuO 2 material. Since 241 Pu decays into 241 Am with a half-life of t ½ = 14.3a, the americium content in the PuO 2 reference of known age could also be calculated and used as a virtual reference (Walker, 1999; Lamontagne et al, 2007, 2013). This method can be used for other elements, where the radioactive decay and half-life are well known.…”

Section: Resultsmentioning

confidence: 99%

Improved Protocol for the Quantification of Actinides (Th, U, Np, Pu, Am, and Cm) Using Electron Probe Microanalysis

et al. 2021

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“…because the EPA‐approved method of alpha spectrometry depends on a minimum of 4 hr of spectrum recording, in addition to the usual difficulties of poor energy resolution and interferences from close‐lying alpha energies of 238 Pu and 228 Th (http://www.epa.gov). TIMS and SIMS will be highly useful to experimentally determine the transmutation of Am dispersed in an inert magnesia matrix, in a fast reactor (Lamontagne et al, ). For studies on trans‐plutonium actinides, international collaborations in terms of availability of actinide isotopes, α‐containment facilities, glove‐box enclosed instruments, human‐resources, and expertise is the best route to generate world‐wide useful and reliable data for safe and efficient use of nuclear energy.…”

Section: Conclusion and Future Perspectivesmentioning

confidence: 99%

A review on the mass spectrometric studies of americium: Present status and future perspective

Aggarwal

2016

Mass Spectrometry Reviews

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The manuscript reviews the various mass spectrometric techniques for analysis and chemical studies of Americium. These methods include thermal ionization mass spectrometry (TIMS), and inductively coupled plasma source mass spectrometry (ICPMS) for the determination of Am isotope ratios and concentration in nuclear fuel samples of interest in nuclear technology, and in complex biological and environmental samples. Ultra-sensitive mass spectrometric techniques of resonance-ionization mass spectrometry (RIMS), and accelerator-based mass spectrometry (AMS) are also discussed. The novel applications of electrospray ionization mass spectrometry (ESIMS) to understand the solution chemistry of Am and other actinides are presented. These studies are important in view of the world-wide efforts to develop novel complexing agents to separate lanthanides and minor actinides (Am, Np, and Cm) for partitioning and transmutation of minor actinides from the point of view of nuclear waste management. These mass spectrometry experiments are also of great interest to examine the covalent character of actinides with increasing atomic number. Studies on gas-phase chemistry of Am and its oxides with Knudsen effusion mass spectrometry (KEMS), Fourier-transform ion cyclotron resonance mass spectrometry (FTICR-MS), and laser-based experiments with reflectron time-of-flight mass spectrometer (R-ToF) are highlighted. These studies are important to understand the fundamental chemistry of 5f electrons in actinides. Requirement of certified isotopic reference materials of Am to improve the accuracy of experimental nuclear data (e.g., the half-life of Am) is emphasized. © 2016 Wiley Periodicals, Inc. Mass Spec Rev.

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Determining the americium transmutation rate and fission rate by post-irradiation examination within the scope of the ECRIX-H experiment

Cited by 8 publications

References 32 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

Improved Protocol for the Quantification of Actinides (Th, U, Np, Pu, Am, and Cm) Using Electron Probe Microanalysis

A review on the mass spectrometric studies of americium: Present status and future perspective

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