Thermodynamic modelling of advanced oxide and carbide nuclear fuels: Description of the U–Pu–O–C systems

Guéneau, C.; Dupin, N.; Sundman, Bo; Martial, Chantal; Dumas, Jean-Christophe; Gossé, Stéphane; Chatain, S.; Bruycker, F. De; Manara, D.; Konings, R.J.M.

doi:10.1016/j.jnucmat.2011.07.033

Cited by 200 publications

(219 citation statements)

References 84 publications

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“…In this context, it appeared that most actinideoxygen phase boundaries should be revisited, especially at high temperature. 8 It seemed then of great interest to apply the current experimental approach to neptunium dioxide.…”

Section: In 1971mentioning

confidence: 99%

Revisiting the melting temperature of NpO2 and the challenges associated with high temperature actinide compound measurements

Böhler

Welland

Bruycker

et al. 2012

Journal of Applied Physics

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This work revisits the melting behaviour of neptunium dioxide, an actinide compound which can be produced in the nuclear fuel during operation, and which has an important impact on the nuclear fuel and waste radioactivity especially on the very long term. The present experimental approach employs remote laser heating under controlled atmosphere and fast pyrometry. This technique circumvents problems encountered by more traditional heating techniques, in particular, the reaction between sample and containment at temperatures beyond 2500 K. In addition, only a small amount of sample material is required, which is an advantage with respect to the radioactivity and limited availability of neptunium. The NpO 2 melting/freezing temperature has been measured to be 3070 K 6 62 K, much higher than previous values (around 2830 K) obtained by more traditional thermal analysis methods. The large amount of experimental data collected allowed a consistent statistical analysis. It seems likely, although not fully evident from the present results, that the high oxygen potential at temperatures around melting leads to a slightly hypo-stoichiometric congruent melting composition, as already observed in other actinide (ThO 2 , PuO 2 ) and lanthanide oxides (e.g., CeO 2 ). Finally, a recently developed phase-field model was used for the simulation of the observed thermograms, allowing a deeper insight in material properties that are difficult to directly measure. For example, a polaron contribution to the high-temperature thermal conductivity, well accepted for the commonly studied actinide oxide UO 2 , is shown here to likely be present in NpO 2 .

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Section: In 1971mentioning

confidence: 99%

Revisiting the melting temperature of NpO2 and the challenges associated with high temperature actinide compound measurements

Böhler

Welland

Bruycker

et al. 2012

Journal of Applied Physics

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“…The research was performed by the method of thermodynamic modelling [14,15], which was successfully used to study inorganic substances at high temperatures in metallurgy, materials science, and physics [8][9][10][11][16][17][18].…”

Section: Methodsmentioning

confidence: 99%

“…In the articles [8,9] systems Pu-O and U-Pu-O-C were investigated. Ho, Kuo, and Hopper [10] studied the behaviour of uranium and plutonium during heating to high temperatures under oxidizing and reducing atmospheres by the method of thermodynamic modelling.…”

Section: Introductionmentioning

confidence: 99%

Thermodynamic analysis of radionuclides behaviour in products of vapour phase hydrothermal oxidation of radioactive graphite

Барбин

Terentiev

Alexeev

et al. 2015

J Radioanal Nucl Chem

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The behaviour of radionuclides was studied by the method of thermodynamic modelling in the wide temperature range 400-3200 K during interaction of radioactive graphite with water vapour, taken in the ratio C (s):H 2 O (g) = 1:10 and 1:20 (by mass). It was determined that the main components of the gaseous phase over the whole temperature range are H 2 O vapour, H 2 , gaseous CO and CO 2 containing radioactive 14 C. Their partial pressures exceed 10 3 Pa. Cs, Sr, Ca, Be, Ni radionuclides, which radioactive graphite contains, form volatile hydroxides, U, Pu radionuclides-volatile oxides. The partial pressure of these radionuclides does not exceed 10 -1 Pa.

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“…The heat capacity of UO 2 Bo Sundman and Christine Guéneau (INSTN and DEN/DANS/DPC/SCCME, CEA Saclay) The use of Computational Thermodynamics to predict properties of multicomponent mater December 5, 2012 12 / 26…”

Section: Heat Never Flows Spontaneously From a Cold Body To A Hot Bodymentioning

confidence: 99%

The Use of Computational Thermodynamics to Predict Properties of Multicomponent Materials for Nuclear Applications

Sundman

Guéneau

2013

EPJ Web of Conferences

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Thermodynamic modelling of advanced oxide and carbide nuclear fuels: Description of the U–Pu–O–C systems

Cited by 200 publications

References 84 publications

Revisiting the melting temperature of NpO2 and the challenges associated with high temperature actinide compound measurements

Revisiting the melting temperature of NpO2 and the challenges associated with high temperature actinide compound measurements

Thermodynamic analysis of radionuclides behaviour in products of vapour phase hydrothermal oxidation of radioactive graphite

The Use of Computational Thermodynamics to Predict Properties of Multicomponent Materials for Nuclear Applications

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