Linking atomic and mesoscopic scales for the modelling of the transport properties of uranium dioxide under irradiation

Bertolus, Marjorie; Freyss, Michel; Dorado, Boris; Martin, Guillaume; Hoang, Kiet; Maillard, Serge; Skorek, Richard; Garcia, Philippe; Valot, C.; Chartier, Alain; Brutzel, L. Van; Fossati, Paul; Grimes, Robin W.; Parfitt, David; Bishop, Clare L.; Murphy, Samuel T.; Rushton, Michael; Staicu, D.; Yakub, E. S.; Nichenko, Sergii; Krack, Matthias; Devynck, Fabien; Ngayam-Happy, Raoul; Govers, Kevin; Deo, Chaitanya; Behera, Rakesh K.

doi:10.1016/j.jnucmat.2015.02.026

Cited by 34 publications

(19 citation statements)

References 90 publications

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“…The latter is in agreement with our DFT þ U calculations showing that this incorporation site is especially favored as compared to U vacancy and Schottky defects with oxygen vacancies aligned along (110) and (111) directions 48 in agreement with earlier studies. 49,50 Moreover, the concentrations of U vacancy and SD(111) tends to confirm that the local disorder is completely annealed at 1673 K.…”

Section: Experimental Evidence Of Xe Incorporation In Schottky Defectmentioning

confidence: 76%

Experimental evidence of Xe incorporation in Schottky defects in UO2

Bès

Martin²,

Vathonne³

et al. 2015

Applied Physics Letters

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Section: Experimental Evidence Of Xe Incorporation In Schottky Defectmentioning

confidence: 76%

Experimental evidence of Xe incorporation in Schottky defects in UO2

Bès

Martin²,

Vathonne³

et al. 2015

Applied Physics Letters

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“…This applies to conditions where the exact temperature distribution is critical or where one is tasked with development and validation of model with predictive capability. 8,17,18 The latter typically involves the ability to predict thermal conductivity as a function of radiation induced microstructure. 19 Another limitation of both techniques is their lack of sensitivity to a thin damage layer resulting from ion beam irradiations, which is an alternative method used to simulate displacement damage caused by energetic neutrons and fission products.…”

Section: Measurement Of Thermal Transport a Standard Approaches mentioning

confidence: 99%

Investigation of thermal transport in composites and ion beam irradiated materials for nuclear energy applications

et al. 2016

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Thermal transport in materials used for energy applications is a physical process directly tied to performance and reliability. As a result, a great deal of effort has been devoted to understanding thermal transport in materials whose ability to conduct heat is critical. Here, our objective is to discuss the utility of laser-based thermoreflectance (TR) approaches that provide microscale measurement of thermal transport. We provide several examples that implement the TR technique to investigate thermal transport in materials used in nuclear energy applications. First, we discuss utility of this technique to measure thermal conductivity in ion irradiated ceramic materials during investigations where the primary objective is to understand the impact of radiation induced crystalline structure defects on thermal transport. We also present the capability of TR approach to resolve thermal conductivity of each layer in tristructural isotropic fuel, silicon carbide fiber composites, and 2nd phase precipitates in uranium silicide. Finally, the ability to measure interface thermal resistance between adjacent layers in composites is demonstrated.

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“…In the nuclear field, there is an increasing demand for more physically based modeling of material properties in order not only to have a limited number of validation irradiations in actual reactor conditions, but also to make more reliable predictions outside of the validation domain. This trend largely applies to nuclear fuel with numerous papers going from first principles calculations to modeling of the fuel microstructure [1]. It is also relevant for neutron absorber materials for which less work has been done.…”

Section: Introductionmentioning

confidence: 99%

“…pure thermal neutron flux in T4 induces no damage due to neutron collisions with atoms in the B 4 C samples because the energy transferred by neutron collisions to a B or C atom is less than its displacement threshold. Moreover the neutron absorption cross-section for the reaction 10 B +n --> 7 Li + 4 He(1) …”

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confidence: 99%

A new methodology for studying neutron absorber materials: First results with boron carbide

Desgranges

Escleine

Bienvenu

et al. 2018

Nuclear Instruments and Methods in Physics Research Section B:

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A new methodology is presented for the study of transmutation damage in B 4 C boron carbide. The B 4 C samples are set in a specially designed sample holder, and irradiated in a neutron thermal flux, at the ILL reactor in our case. After the description of the sample holder and the irradiation conditions, the first post-irradiation examinations by Secondary Ion Mass Spectroscopy (SIMS), X-Ray Diffraction (XRD) and Secondary Electron Microscopy (SEM) are detailed. The first results obtained on a B 4 C disk with natural 10 B composition prove the efficiency of the methodology.

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Linking atomic and mesoscopic scales for the modelling of the transport properties of uranium dioxide under irradiation

Cited by 34 publications

References 90 publications

Experimental evidence of Xe incorporation in Schottky defects in UO2

Experimental evidence of Xe incorporation in Schottky defects in UO2

Investigation of thermal transport in composites and ion beam irradiated materials for nuclear energy applications

A new methodology for studying neutron absorber materials: First results with boron carbide

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