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125 results on '"Laboratoire de Modélisation Multi-échelles des Combustibles (LM2C)"'

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1. Modelling the onset and propagation of damage of matrix/inclusion type heterogeneous media with differential swelling

2. Surface and grain boundary interdiffusion during the sintering of mixed oxides fuels - a Finite Volume Method simulation

3. Changes in voids induced by ion irradiations in UO2: In situ TEM studies

4. Assessment of atomistic data for predicting the phase diagram and defect thermodynamics in UO$_2$

5. Conductivité thermique d'une céramique affectée par un réseau de fissures localisées aux joints de granulats : simulations 2D de l'effet d'une distribution bimodale de taille de granulats

6. Materials for Sustainable Nuclear Energy: A European Strategic Research and Innovation Agenda for All Reactor Generations

7. Compatibility of UN with refractory metals (V, Nb, Ta, Cr, Mo, and W): an $ab\ initio$ approach to interface reactions and diffusion behavior

8. Caractérisation et simulation de microstructures de céramiques d'UO2 présentant un réseau de porosité filamentaire

9. One-dimensional modeling of bulk cationic interdiffusion in mixed oxides (U,Pu)O$_2$ and analysis of homogenization within a microstructure using a finite difference method

10. Multiscale modelling in nuclear ferritic steels: from nano-sized defects to embrittlement

11. Stochastic homogenization : a short proof of the annealed Calderón-Zygmund estimate

12. Atomic scale investigation of thermodynamic and defect properties of (U,Pu)O2 mixed oxide

13. Calculations of thermodynamical properties of U3Si2

14. Development of a solute and defect concentration dependant Ising model for the study of transmutation induced segregation in neutron irradiated W-(Re, Os) systems

15. Representative volume elements for matrix-inclusion composites -- a computational study on periodizing the ensemble

16. First principles model for voids decorated by transmutation solutes: Short-range order effects and application to neutron irradiated tungsten

17. Solubility and vacancy-mediated interdiffusion in the Zr-Nb-Cr system

18. Editorial: Computational defect properties

19. Development and application of an interatomic potential for the investigation of mixed oxide compounds containing Americium

20. Two fuel performance codes of the PLEIADES platform: ALCYONE and GERMINAL

21. Using basic research to improve the simulation of MOX fuel behaviour

22. Homogenization approach to model the thermal-mechanical behavior of melting fuel material

23. TEM characterisation of helium platelets in implanted uranium dioxide

24. Advances on GenIV structural and fuel materials and cross-cutting activities between fission and fusion

25. Modelling and measuring methods for PCI characterization

26. Uranium carbide oxidation from 873 K to 1173 K

27. Radiation-induced micro-structures as ground states of a Swift-Hohenberg energy functional

28. Characterization of an UO2 ceramic via Raman imaging and electron back-scattering diffraction

29. Novel insight into the chemical analysis of light elements in oxycarbides

30. Study of the TiC{1-x} – TiO2 reactive interface

31. Identification of vacancy-type defects in UO2

32. Structural features of aliovalent substitutions in UO2

33. Galactic cold cores

34. Galactic cold cores

35. Determination of Krypton Diffusion Coefficients in Uranium Dioxide Using Atomic Scale Calculations

36. Density Functional Theory Calculations of UO2 Oxidation: Evolution of UO2+x, U4O9–y, U3O7, and U3O8

37. Study of the correlation between fuel engineering properties and point defects

38. Utilisation de la NRA pour l'étude de l'interdiffusion C / O dans les composés de la famille IVb (Ti, Zr, Hf)

39. Structural characteristics of hy- perstoichiometric uranium oxides

40. Thin film samples: a new methodology for investigating the mechanisms of fission gas releases from nuclear fuel during a LOCA

41. Planck intermediate results: XXXV. Probing the role of the magnetic field in the formation of structure in molecular clouds

42. Recent developments in the ABINIT software package

43. From in Situ HT-ESEM Observations to Simulation: How Does Polycrystallinity Affects the Sintering of CeO2 Microspheres?

44. An auto-catalytic mechanism to model the fission gas release between 500°C and 800°C on UO2 irradiated fuel

45. Strain relaxation in He implanted UO 2 polycrystals under thermal treatment: an in-situ XRD study

46. Is UO2 irradiation resistance due to its unusual high temperature behaviour?

47. Study of xenon thermal migration in sintered titanium nitride using nuclear micro-probe

48. On the origin of the sigmoid shape in the UO2 oxidation weight gain curves

49. Helium behavior in α-SiC ceramics investigated by NRA technique

50. The study of the UO(2+x) crystalline structure with high-resolution neutron diffraction experiment

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