Ceramic processing of uranium–plutonium mixed oxide fuels (U1−yPuy)O2 with high plutonium content

Vauchy, Romain; Robisson, Anne-Charlotte; Audubert, Fabienne; Hodaj, F.

doi:10.1016/j.ceramint.2014.03.104

Cited by 25 publications

(20 citation statements)

References 26 publications

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“…As expected, stoichiometric U 0.7 Pu 0.3 O 2.00 pellets exhibit a single face-centered cubic phase with a lattice parameter in good agreement with Vegard's law [15]. Due to the high plutonium content of the MOX (over 20% of actinide content) under-stoichiometric U 0.7 Pu 0.3 O 2Àx pellets exhibit a biphasic composition at room temperature [18].…”

Section: Mox Pellets Preparationsupporting

confidence: 53%

“…This method is known to give a fully homogeneous solid solution [14] without any milling step before sintering, as compared to powder metallurgy [15]. This powder has been pressed into green pellets and was sintered at 1600 C during 8 h. The atmosphere applied during sintering was Ar-4%H 2 for the under-stoichiometric U 0.7 Pu 0.3 O 2Àx pellets, and Ar-4%H 2 with 2000 ppm H 2 O for stoichiometric U 0.7 Pu 0.3 O 2.00 pellets [16].…”

Section: Mox Pellets Preparationmentioning

confidence: 99%

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Interaction study between MOX fuel and eutectic lead–bismuth coolant

Vigier

Popa

Tyrpekl

et al. 2015

Journal of Nuclear Materials

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h i g h l i g h t s g r a p h i c a l a b s t r a c t Interaction tests are performed between U 0.7 Pu 0.3 O 2 fuel and Pb 0.45 Bi 0.55 liquid metal coolant. Oxygen concentration in liquid metal, stoichiometry of the MOX and interaction temperature are studied. No chemical reaction detected. Less than 0.01% to 0.65% of the pellets is released into the coolant depending to the conditions. a b s t r a c tIn the frame of the MYRRHA reactor project, the interaction between fuel pellets and the reactor coolant is essential for safety evaluations, e.g. in case of a pin breach. Therefore, interaction tests between uraniumeplutonium mixed oxide (MOX) pellets and molten lead bismuth eutectic (LBE) have been performed and three parameters were studied, namely the interaction temperature (500 C and 800 C), the oxygen content in LBE and the stoichiometry of the MOX (U 0.7 Pu 0.3 O 2Àx and U 0.7 Pu 0.3 O 2.00 ). After 50 h of interaction in closed containers, the pellet integrity was preserved in all cases. Whatever the conditions, neither interaction compounds (crystalline or amorphous) nor lead and bismuth diffusion into the surface regions of the MOX pellets has been detected. In most of the conditions, actinide releases into LBE were very limited (in the range of 0.01e0.15 mg), with a homogeneous release of the different actinides present in the MOX. Detected values were significantly higher in the 800 C and low LBE oxygen content tests for both U 0.7 Pu 0.3 O 2Àx and U 0.7 Pu 0.3 O 2.00 , with 1e2 mg of actinide released in these conditions.

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Section: Mox Pellets Preparationsupporting

confidence: 53%

Section: Mox Pellets Preparationmentioning

confidence: 99%

Interaction study between MOX fuel and eutectic lead–bismuth coolant

Vigier

Popa

Tyrpekl

et al. 2015

Journal of Nuclear Materials

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“…Each of these two mixtures was then micronized by co-milling in order to increase the U-Pu distribution homogeneity in the final material. The detailed fabrication process is described elsewhere [28]. …”

Section: Sample Preparationmentioning

confidence: 99%

Room-temperature oxidation of hypostoichiometric uranium–plutonium mixed oxides U1−yPuyO2−x – A depth-selective approach

Vauchy

Robisson

Belin

et al. 2015

Journal of Nuclear Materials

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“…Stoichiometric MOX U 1−y Pu y O 2.00 has a fluorite structure with a lattice parameter following Vegard's law for all range of composition (0 ≤ y ≤ 1). 4 In the case of substoichiometric MOX, a single fluorite structure is maintained for low plutonium contents (y < 0.2), while 2 phases are observed for higher plutonium contents (y > 0.2). 5 In the case of U 0.7 Pu 0.3 O 2-x , both phases exhibit fluorite structures, the first one with a O/M ratio close to 2.00, while the second has a lower oxygen content.…”

Section: ■ Introductionmentioning

confidence: 98%

Structural Investigation of (U_0.7Pu_0.3)O_2-x Mixed Oxides

et al. 2015

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Uranium-plutonium mixed oxide containing 30% of plutonium is a candidate fuel for several fast neutron and accelerator driven reactor systems. In this work, a detailed structural investigation on sol-gel synthesized stoichiometric U0.7Pu0.3O2.00 and substoichiometric U0.7Pu0.3O2-x, using X-ray diffraction (XRD), oxygen 17 magic angle spinning nuclear magnetic resonance ((17)O MAS NMR) and X-ray absorption spectroscopy is described. As observed by XRD, the stoichiometric U0.7Pu0.3O2.00 is monophasic with a lattice parameter in good agreement with Vegard's law, while the substoichiometric U0.7Pu0.3O2-x material is biphasic. Solid solution ideality in terms of a random distribution of metal atoms is proven for U0.7Pu0.3O2.00 with (17)O MAS NMR. X-ray absorption near-edge structure (XANES) spectroscopy shows the presence of plutonium(III) in U0.7Pu0.3O2-x. Extended X-ray absorption fine-structure (EXAFS) spectroscopy indicates a similar local structure around both cations, and comparison with XRD indicates a close similarity between uranium and plutonium local structures and the long-range ordering.

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Ceramic processing of uranium–plutonium mixed oxide fuels (U1−yPuy)O2 with high plutonium content

Cited by 25 publications

References 26 publications

Interaction study between MOX fuel and eutectic lead–bismuth coolant

Interaction study between MOX fuel and eutectic lead–bismuth coolant

Room-temperature oxidation of hypostoichiometric uranium–plutonium mixed oxides U1−yPuyO2−x – A depth-selective approach

Structural Investigation of (U_0.7Pu_0.3)O_2-x Mixed Oxides

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Ceramic processing of uranium–plutonium mixed oxide fuels (U1−yPuy)O2 with high plutonium content

Cited by 25 publications

References 26 publications

Interaction study between MOX fuel and eutectic lead–bismuth coolant

Interaction study between MOX fuel and eutectic lead–bismuth coolant

Room-temperature oxidation of hypostoichiometric uranium–plutonium mixed oxides U1−yPuyO2−x – A depth-selective approach

Structural Investigation of (U0.7Pu0.3)O2-x Mixed Oxides

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Structural Investigation of (U_0.7Pu_0.3)O_2-x Mixed Oxides