E-LIB Suche - Ergebnisse für: Aubrun, I.

1

Experimental and numerical study of fracture mechanisms in ..:

Gatt, J.-M. ; Sercombe, J. ; Aubrun, I..
Engineering Failure Analysis. 47 (2015) - p. 299-311 , 2015

Link: https://doi.org/10.1016/..

2

Evidence of tellurium iodide compounds in a power-ramped ir..:

Desgranges, L. ; Riglet-Martial, Ch. ; Aubrun, I....
Journal of Nuclear Materials. 437 (2013) 1-3 - p. 409-414 , 2013

Link: https://doi.org/10.1016/..

3

Power ramped cladding stresses and strains in 3D simulation..:

Sercombe, J. ; Aubrun, I. ; Nonon, C.
Nuclear Engineering and Design. 242 (2012) - p. 164-181 , 2012

Link: https://doi.org/10.1016/..

4

HIGH BURNUP CHANGES IN UO2FUELS IRRADIATED UP TO 83 GWD/T I..:

Noirot, J. ; Aubrun, I. ; Desgranges, L....
Nuclear Engineering and Technology. 41 (2009) 2 - p. 155-162 , 2009

Link: https://doi.org/10.5516/..

5

Behavior of a Defective Nuclear Fuel Rod in Dry Storage Con..:

Desgranges, L. ; Ferroud-Plattet, M. P. ; Alloncle, R....
Nuclear Technology. 163 (2008) 2 - p. 252-260 , 2008

Link: https://doi.org/10.13182..

6

HIGH BURNUP CHANGES IN UO 2 FUELS IRRADIATED UP TO 83 GWd/t..:

Noirot, J ; Aubrun, I ; Desgranges, L...
hal-02010442. , 2009

Link: https://hal.science/hal-..

7

HIGH BURNUP CHANGES IN UO 2 FUELS IRRADIATED UP TO 83 GWd/t..:

Noirot, J ; Aubrun, I ; Desgranges, L...
hal-02010442. , 2009

Link: https://hal.archives-ouv..

8

HIGH BURNUP CHANGES IN UO 2 FUELS IRRADIATED UP TO 83 GWd/t..:

Noirot, J ; Aubrun, I ; Desgranges, L...
hal-02010442. , 2009

Link: https://hal.science/hal-..

9

A Method for the Quantification of Total Xenon Concentratio..:

Hanifi, K. ; Noirot, L. ; Bienvenu, Ph....
Microscopy and Microanalysis. 20 (2014) S3 - p. 1842-1843 , 2014

Link: https://doi.org/10.1017/..

10

2D(r,θ) Simulations of the HBC-4 Power-to-Melt Experiment w..:

Sercombe, J. ; D'Ambrosi, V. ; Béjaoui, S..
Nuclear Technology. 210 (2023) 2 - p. 269-284 , 2023

Link: https://doi.org/10.1080/..

11

Fission products at the fuel-cladding interface of PWR fuel..:

Schneider, C. ; Fayette, L. ; Zacharie-Aubrun, I....
Journal of Nuclear Materials. 585 (2023) - p. 154600 , 2023

Link: https://doi.org/10.1016/..

12

Presentation of the xM3 Test Case of the P2M Simulation Exe..:

D'Ambrosi, V. ; Sercombe, J. ; Béjaoui, S....
Nuclear Technology. 210 (2023) 2 - p. 285-307 , 2023

Link: https://doi.org/10.1080/..

13

Study of the hardness and Young's modulus at the fuel-cladd..:

Schneider, C. ; Fayette, L. ; Zacharie-Aubrun, I....
Journal of Nuclear Materials. 560 (2022) - p. 153511 , 2022

Link: https://doi.org/10.1016/..

14

Microstructural Analysis of Zirconia at the Fuel-Cladding I..:

Schneider, C. ; Fayette, L. ; Zacharie-Aubrun, I....
Oxidation of Metals. 96 (2021) 3-4 - p. 295-306 , 2021

Link: https://doi.org/10.1007/..

15

Effects of irradiation on mechanical properties of nuclear ..:

Zacharie-Aubrun, I. ; Henry, R. ; Blay, Th....
Journal of Nuclear Materials. 547 (2021) - p. 152821 , 2021

Link: https://doi.org/10.1016/..