Impact of advanced nuclear fuel cycle IMF on geological repository performance

Pritrsky, Jozef; Nečas, Vladimı́r

doi:10.1016/j.pnucene.2011.09.005

Cited by 4 publications

(5 citation statements)

References 7 publications

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“…1,2 However, it produces radiotoxic waste that must be securely stored for thousands of years. [3][4][5] Transuranic elements (TRU; i.e., Pu, Am, Np, Cm) are largely responsible for the long-term radioactivity of spent nuclear fuel and the heat generated by these elements limits the storage capacity of geological facilities (e.g., Yucca Mountain). 4,6,7 The amount of transuranic species that must be stored can be reduced by incorporating them into nuclear fuels and "burning up" (transmuting) these elements in-reactor.…”

Section: Introductionmentioning

confidence: 99%

“…[3][4][5] Transuranic elements (TRU; i.e., Pu, Am, Np, Cm) are largely responsible for the long-term radioactivity of spent nuclear fuel and the heat generated by these elements limits the storage capacity of geological facilities (e.g., Yucca Mountain). 4,6,7 The amount of transuranic species that must be stored can be reduced by incorporating them into nuclear fuels and "burning up" (transmuting) these elements in-reactor. 4,[8][9][10] Inert matrix fuels, which consist of TRU species embedded in a neutron transparent (inert) material, have been proposed as nuclear fuels for use in Generation IV nuclear reactors.…”

Section: Introductionmentioning

confidence: 99%

“…4,6,7 The amount of transuranic species that must be stored can be reduced by incorporating them into nuclear fuels and "burning up" (transmuting) these elements in-reactor. 4,[8][9][10] Inert matrix fuels, which consist of TRU species embedded in a neutron transparent (inert) material, have been proposed as nuclear fuels for use in Generation IV nuclear reactors. 8,[11][12][13][14] Cubic zirconia (ZrO2), which adopts a fluorite-type structure, has been widely proposed for use as an inert matrix fuel due to its chemical durability, resistance to radiation damage, and high melting point (in addition to its low neutron absorption cross-section).…”

Section: Introductionmentioning

confidence: 99%

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Investigation of the Thermal Stability of Nd_xSc_yZr_1–x–yO_2−δ Materials Proposed for Inert Matrix Fuel Applications

2016

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Inert matrix fuels (IMF) consist of transuranic elements (i.e., Pu, Am, Np, Cm) embedded in a neutron transparent (inert) matrix and can be used to "burn up" (transmute) these elements in current or Generation IV nuclear reactors. Yttria-stabilized zirconia has been extensively studied for IMF applications, but the low thermal conductivity of this material limits its usefulness. Other elements can be used to stabilize the cubic zirconia structure, and the thermal conductivity of the fuel can be increased through the use of a lighter stabilizing element. To this end, a series of Nd(x)Sc(y)Zr(1-x-y)O(2-δ) materials has been synthesized via a co-precipitation reaction and characterized by multiple techniques (Nd was used as a surrogate for Am). The long-range and local structures of these materials were studied using powder X-ray diffraction, scanning electron microscopy, and X-ray absorption spectroscopy. Additionally, the stability of these materials over a range of temperatures has been studied by annealing the materials at 1100 and 1400 °C. It was shown that the Nd(x)Sc(y)Zr(1-x-y)O(2-δ) materials maintained a single cubic phase upon annealing at high temperatures only when both Nd and Sc were present with y ≥ 0.10 and x + y > 0.15.

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Investigation of the Thermal Stability of Nd_xSc_yZr_1–x–yO_2−δ Materials Proposed for Inert Matrix Fuel Applications

2016

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“…5,6 Spent nuclear fuel must be stored for long periods of time due to the presence of transuranic species (TRUs; i.e., Pu, Np, Am, and Cm), which account for the majority of the fuel radiotoxicity after several hundred years. [7][8][9] These TRU elements could be eliminated by "burning up" (i.e., transmuting) the elements in commercial nuclear reactors, and inert matrix fuels (IMFs) have been proposed as a means for burning up TRU elements in current generation reactors. 7,[9][10][11][12] An IMF consists of TRU elements embedded in a neutron transparent (inert) material.…”

Section: Introductionmentioning

confidence: 99%

“…[7][8][9] These TRU elements could be eliminated by "burning up" (i.e., transmuting) the elements in commercial nuclear reactors, and inert matrix fuels (IMFs) have been proposed as a means for burning up TRU elements in current generation reactors. 7,[9][10][11][12] An IMF consists of TRU elements embedded in a neutron transparent (inert) material. Cubic zirconia (ZrO 2 ), which adopts the fluorite structure, has often been proposed for use as IMFs due to its low neutron cross section, chemical durability, and resistance to radiation damage.…”

Section: Introductionmentioning

confidence: 99%

Investigation of Nd_xY_0.25–_xZr_0.75O_1.88 inert matrix fuel materials made by a co-precipitation synthetic route

Hayes

Grosvenor

2016

Can. J. Chem.

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Yttria-stabilized zirconia (YSZ) is a material that is being considered for use as an inert matrix fuel in nuclear reactors, but a complete characterization of these materials is required for them to be licensed for use. A series of Nd x Y 0.25-x Zr 0.75 O 1.88 materials have been synthesized using a co-precipitation method, and the thermal stability of these materials has been studied by annealing them at 1400 and 1500°C. (Nd was used as surrogate for Am.) The long-range and local structures of the materials were characterized via powder X-ray diffraction, scanning electron microscopy, wavelength dispersive spectroscopy, and X-ray absorption spectroscopy at the Zr K-and Y K-edges. These results were compared with the previous characterization of Nd-YSZ materials synthesized using a ceramic method. The results indicated that the ordering in the local metal-oxygen polyhedral remains relatively unaffected by the synthetic method, but there was increased long-range disorder in the materials prepared by the co-precipitation method. Further, it was found that the materials produced by the co-precipitation method were unexpectedly unstable when annealed at high temperature. This study highlights the importance of determining the effect of synthetic method on material properties and demonstrates how the co-precipitation route could be used to produce inert matrix fuels.Key words: XAS, ceramics, stabilized zirconia, nuclear energy, XRD.Résumé : La zircone stabilisée par oxyde d'yttrium (YSZ) constitue un matériau dont l'utilisation est envisagée comme combustible à matrice inerte dans les réacteurs nucléaires, mais une caractérisation complète de tels matériaux est nécessaire pour que leur utilisation puisse être autorisée. Nous avons synthétisé une série de matériaux de formule Nd x Y 0,25-x Zr 0,75 O 1,88 par une méthode de coprécipitation et étudié la stabilité thermique de ces matériaux en les soumettant à un recuit à 1 400 et 1 500°C. (Le Nd a été employé comme substitut de l'Am.) Par la suite, nous avons caractérisé les matériaux en effectuant des analyses structurales d'ordre à longue et à courte distance au moyen de techniques de diffraction des rayons X sur poudre, de microscopie électronique à balayage, de spectroscopie de dispersion des longueurs d'onde et de spectroscopie d'absorption des rayons X au seuil K du Zr et de l'Y. Nous avons comparé ces résultats avec les analyses antérieures de caractérisation de matériaux de Nd-YSZ préparés à l'aide d'une méthode de synthèse de céramiques. Les résultats ont montré que la méthode de synthèse a relativement peu d'influence sur l'ordre à courte distance dans le polyèdre métal-oxygène, tandis qu'une augmentation du désordre à longue distance a été observée dans les matériaux synthétisés par la méthode de coprécipitation. De plus, nous avons observé que les matériaux produits par la méthode de coprécipitation présentaient une instabilité imprévue lorsqu'ils étaient soumis au recuit à haute température. La présente étude souligne l'importance de déterminer l...

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Preparation and thermal physical properties of MgO-(Nd1-Y )2(Zr1-Ce )2O7 composite ceramics as a candidate for inert matrix fuel

Li,

Wang,

Wang

et al. 2023

Ceramics International

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Impact of advanced nuclear fuel cycle IMF on geological repository performance

Cited by 4 publications

References 7 publications

Investigation of the Thermal Stability of Nd_xSc_yZr_1–x–yO_2−δ Materials Proposed for Inert Matrix Fuel Applications

Investigation of the Thermal Stability of Nd_xSc_yZr_1–x–yO_2−δ Materials Proposed for Inert Matrix Fuel Applications

Investigation of Nd_xY_0.25–_xZr_0.75O_1.88 inert matrix fuel materials made by a co-precipitation synthetic route

Preparation and thermal physical properties of MgO-(Nd1-Y )2(Zr1-Ce )2O7 composite ceramics as a candidate for inert matrix fuel

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Impact of advanced nuclear fuel cycle IMF on geological repository performance

Cited by 4 publications

References 7 publications

Investigation of the Thermal Stability of NdxScyZr1–x–yO2−δ Materials Proposed for Inert Matrix Fuel Applications

Investigation of the Thermal Stability of NdxScyZr1–x–yO2−δ Materials Proposed for Inert Matrix Fuel Applications

Investigation of NdxY0.25–xZr0.75O1.88 inert matrix fuel materials made by a co-precipitation synthetic route

Preparation and thermal physical properties of MgO-(Nd1-Y )2(Zr1-Ce )2O7 composite ceramics as a candidate for inert matrix fuel

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Investigation of the Thermal Stability of Nd_xSc_yZr_1–x–yO_2−δ Materials Proposed for Inert Matrix Fuel Applications

Investigation of the Thermal Stability of Nd_xSc_yZr_1–x–yO_2−δ Materials Proposed for Inert Matrix Fuel Applications

Investigation of Nd_xY_0.25–_xZr_0.75O_1.88 inert matrix fuel materials made by a co-precipitation synthetic route