Oxidation of accident tolerant fuel candidates

Johnson, Kenneth W.; Ström, Valter; Wallenius, Janne; Lopes, Denise Adorno

doi:10.1080/00223131.2016.1262297

Cited by 17 publications

(11 citation statements)

References 17 publications

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“…In dry oxidation condition, U 3 O 8 and UO 2 are major oxidation product [21]. While in the appearance of water, typical hypothesis for accident scenario, hydrogen gas is proposed to form [22]. In low oxygen partial pressure, i.e.…”

Section: Resultsmentioning

confidence: 99%

Radiation-induced grain subdivision and bubble formation in U3Si2 at LWR temperature

Yao

Gong

et al. 2018

Journal of Nuclear Materials

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U 3 Si 2 , an advanced fuel form proposed for light water reactors (LWR), has excellent thermal conductivity and a higher fissile element density. However, limited understanding of the radiation performance and fission gas behavior of U 3 Si 2 is available at LWR conditions. This study explores the irradiation behavior of U 3 Si 2 by 300 KeV Xe + ion beam bombardment combining with in-situ transmission electron microscopy (TEM) observation. The crystal structure of U 3 Si 2 is stable against radiation-induced amorphization at 350 °C even up to a very high dose of 64 displacements per atom (dpa). Grain subdivision of U 3 Si 2 occurs at a relatively low dose of 0.8 dpa and continues to above 48 dpa, leading to the formation of high-density nanoparticles. Nano-sized Xe gas bubbles prevail at a dose of 24 dpa, and Xe bubble coalescence was identified with an increase of irradiation dose. The volumetric swelling resulting from Xe gas bubble formation and coalescence was estimated with respect to radiation dose, and a 2.2% volumetric swelling was observed for U 3 Si 2 irradiated at 64 dpa considering fission gas only.

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Section: Resultsmentioning

confidence: 99%

Radiation-induced grain subdivision and bubble formation in U3Si2 at LWR temperature

Yao

Gong

et al. 2018

Journal of Nuclear Materials

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“…To satisfy the ever-increasing demand for nuclear safety, intensive efforts have been recently devoted to the development of uranium sesquisilicide (U 3 Si 2 ) and uranium mononitride (UN), owing to their high thermal conductivities and high uranium densities. 1,2 Different from UO 2 , UN and U 3 Si 2 can lower the centreline temperature during operation and increase the melting margin. 3 In particular, UN exhibits low fission gas release and good irradiation stability, 4–7 and U 3 Si 2 may have favourable swelling characteristics 8,9 due to its long potential fuel cycle benefit.…”

Section: Introductionmentioning

confidence: 95%

Understanding xenon and vacancy behavior in UO₂, UN and U₃Si₂: a comparative DFT+Ustudy

Zhao

Sun

Liu

et al. 2023

Phys. Chem. Chem. Phys.

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“…This fuel presents various interesting properties such as high fissile density, excellent thermal conductivity and good tolerance for minor actinide inclusion. However, experimental data on nitride fuels is scarce since it suffers from several drawbacks: it should optimally be enriched in 15 N, it was believed not to be compatible with water until a recent study in steam 1 and the focus has historically been on oxide fuels. Modeling has an important role to play in the characterization, choice of experiments and licensing process, especially because experimental fuel testing is expensive and burdensome (need for hotcells).…”

Section: Introductionmentioning

confidence: 99%

Transport properties in dilute UN(X) solid solutions (X=Xe,Kr)

et al. 2016

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Uranium nitride (UN) is a candidate fuel for current GEN III fission reactors, for which it is investigated as an accident-tolerant fuel, as well as for future GEN IV reactors. In this study, we investigate the kinetic properties of gas fission products (Xe and Kr) in UN. Binding and migration energies are obtained using density functional theory, with an added Hubbard correlation to model f -electrons, and the Occupation Matrix Control scheme to avoid metastable states. These energies are then used as input for the Self-Consistent Mean Field method which enables to determine transport coefficients for vacancy-mediated diffusion of Xe and Kr on the U-sublattice. The magnetic ordering of the UN structure is explicitly taken into account, for both energetic and transport properties. Solute diffusivities are compared with experimental measurements and the effect of various parameters on the theoretical model is carefully investigated. We find that kinetic correlations are very strong in this system, and that despite atomic migration anisotropy, macroscopic solute diffusivities show limited anisotropy. Our model indicates that the discrepancy between experimental measurements probably results from different irradiation conditions, and hence different defect concentrations.

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Oxidation of accident tolerant fuel candidates

Cited by 17 publications

References 17 publications

Radiation-induced grain subdivision and bubble formation in U3Si2 at LWR temperature

Radiation-induced grain subdivision and bubble formation in U3Si2 at LWR temperature

Understanding xenon and vacancy behavior in UO₂, UN and U₃Si₂: a comparative DFT+Ustudy

Transport properties in dilute UN(X) solid solutions (X=Xe,Kr)

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Oxidation of accident tolerant fuel candidates

Cited by 17 publications

References 17 publications

Radiation-induced grain subdivision and bubble formation in U3Si2 at LWR temperature

Radiation-induced grain subdivision and bubble formation in U3Si2 at LWR temperature

Understanding xenon and vacancy behavior in UO2, UN and U3Si2: a comparative DFT+Ustudy

Transport properties in dilute UN(X) solid solutions (X=Xe,Kr)

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Understanding xenon and vacancy behavior in UO₂, UN and U₃Si₂: a comparative DFT+Ustudy