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Riglet-Martial, Ch.
19  results:
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1

In situ control of oxygen partial pressure in a buffered UO..:

Khair, M. ; Riglet-Martial, Ch. ; Matheron, P....
Journal of the European Ceramic Society.  40 (2020)  4 - p. 1626-1638 , 2020
Link: https://doi.org/10.1016/..
 
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2

Experimental evidence of oxygen thermo-migration in PWR UO2..:

Riglet-Martial, Ch. ; Sercombe, J. ; Lamontagne, J....
Journal of Nuclear Materials.  480 (2016)  - p. 32-39 , 2016
Link: https://doi.org/10.1016/..
 
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3

Experimental evidence of the formation of a new chemical ph..:

Desgranges, L. ; Lamontagne, J. ; Riglet-Martial, Ch..
Journal of Nuclear Materials.  457 (2015)  - p. 246-251 , 2015
Link: https://doi.org/10.1016/..
 
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4

Thermodynamics of chromium in UO2 fuel: A solubility model:

Riglet-Martial, Ch. ; Martin, Ph. ; Testemale, D....
Journal of Nuclear Materials.  447 (2014)  1-3 - p. 63-72 , 2014
Link: https://doi.org/10.1016/..
 
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5

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/..
 
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6

Speciation and release kinetics of the fission products Mo,..:

Riglet-Martial, Ch ; Sercombe, J ; Pontillon, Yves
cea-02400191.  , 2018
Link: https://hal-cea.archives..
 
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7

Speciation and release kinetics of the fission products Mo,..:

Riglet-Martial, Ch ; Sercombe, J ; Pontillon, Yves
cea-02400191.  , 2018
Link: https://hal-cea.archives..
 
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8

Behaviour of fission products in UO2: Experimental characte..:

Rochedy, M. ; Klosek, V. ; Riglet-Martial, C....
Journal of Nuclear Materials.  581 (2023)  - p. 154450 , 2023
Link: https://doi.org/10.1016/..
 
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9

Modeling of fission product release during severe accidents..:

Germain, A. ; Sercombe, J. ; Riglet-Martial, C....
Nuclear Engineering and Design.  393 (2022)  - p. 111778 , 2022
Link: https://doi.org/10.1016/..
 
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10

Modeling high burnup fuel thermochemistry, fission product ..:

Germain, A. ; Sercombe, J. ; Riglet-Martial, C....
Journal of Nuclear Materials.  561 (2022)  - p. 153527 , 2022
Link: https://doi.org/10.1016/..
 
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11

Coupled modeling of irradiated fuel thermochemistry and gas..:

Germain, A. ; Sercombe, J. ; Riglet-Martial, C....
Journal of Nuclear Materials.  560 (2022)  - p. 153429 , 2022
Link: https://doi.org/10.1016/..
 
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12

Modeling of Pellet Cladding Interaction:

, In: Comprehensive Nuclear Materials,
Sercombe, Jerome ; Michel, Bruno ; Riglet-Martial, Chantal. - p. 417-465 , 2020
Link: https://doi.org/10.1016/..
 
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13

3D simulation of a power ramp including fuel thermochemistr..:

Konarski, P. ; Sercombe, J. ; Riglet-Martial, C....
Journal of Nuclear Materials.  519 (2019)  - p. 104-120 , 2019
Link: https://doi.org/10.1016/..
 
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14

3D thermo-chemical–mechanical simulation of power ramps wit..:

Baurens, B. ; Sercombe, J. ; Riglet-Martial, C....
Journal of Nuclear Materials.  452 (2014)  1-3 - p. 578-594 , 2014
Link: https://doi.org/10.1016/..
 
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15

Evidence for H2S gas as an intermediate species in the reac..:

Chartier, David ; Joussot-Dubien, Christophe ; Quinton, Damien...
International Journal of Hydrogen Energy.  36 (2011)  19 - p. 12121-12129 , 2011
Link: https://doi.org/10.1016/..
 
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