C. Pokor - Concepedia

Author

C. Pokor

Chimie Moléculaire, Macromoléculaire, Matériaux

Also Known As

C Pokor, C. Pokor, Cedric Pokor, Cédric Pokor, Pokor, C., Pokor, Cédric

Publications

495

Citations

H-Index

Concepts

All Affiliations

Chimie Moléculaire, Macromoléculaire, Matériaux Commissariat à l'Énergie Atomique et aux Énergies Alternatives CEA Paris-Saclay Direction des Energies Institut polytechnique de Grenoble

About

C. Pokor is an author at Chimie Moléculaire, Macromoléculaire, Matériaux specializing in engineering, materials science, and microstructure.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	10	10	446
2	Materials Science	9	9	432
3	Mechanical Engineering	6	6	328
4	Materials Engineering	2	2	38
5	Applied Physics	1	1	19

C. Pokor

Publications

457

Citations

H-Index

Page 1

	Year	Citations
Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part I: Evolution of the microstructure C. Pokor, Y. Bréchet, Philippe Dubuisson, Journal of Nuclear Materials Materials ScienceStainless SteelsDamage MechanismEngineeringExperimental Investigation	2004	154
Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part II: Irradiation induced hardening C. Pokor, Y. Bréchet, Philippe Dubuisson, Journal of Nuclear Materials Materials ScienceDamage MechanismEngineeringExperimental InvestigationCorrosion	2004	94
Tomographic atom probe characterization of the microstructure of a cold worked 316 austenitic stainless steel after neutron irradiation Auriane Etienne, B. Radiguet, P. Pareige, Journal of Nuclear Materials Materials ScienceEngineeringPhysicsCorrosionAustenitic Stainless Steel	2008	51
Investigations on the mechanisms of PWSCC of strain hardened austenitic stainless steels Thierry Couvant, L. Legras, C. Pokor, Materials ScienceEngineeringSevere Plastic DeformationCorrosionMechanical Engineering	2007	32
Effect of irradiation defects on the work hardening behavior C. Pokor, X. Averty, Y. Bréchet, Scripta Materialia Materials ScienceEngineeringRadiation-hard DesignSolid MechanicsDefect Tolerance	2003	29
Irradiation creep of SA 304L and CW 316 stainless steels: Mechanical behaviour and microstructural aspects. Part I: Experimental results J. Garnier, Yves Bréchet, M. Delnondedieu, Journal of Nuclear Materials Materials ScienceHigh Temperature MaterialsEngineeringSuperalloyMechanical Engineering	2011	21
Correlation of radiation-induced changes in microstructure/microchemistry, density and thermo-electric power of type 304L and 316 stainless steels irradiated in the Phénix reactor Alexandra Renault Laborne, P. Gavoille, J. Malaplate, Journal of Nuclear Materials Materials ScienceMaterials EngineeringRadiation-induced ChangesEngineeringPhénix Reactor	2015	19
TEM and EFTEM characterization of solution annealed 304L stainless steel irradiated in PHENIX, up to 36dpa and at 390°C A. Renault, J. Malaplate, C. Pokor, Journal of Nuclear Materials Materials EngineeringMaterials ScienceNuclear CeramicEngineeringStainless Steel	2011	19
Analysis of mechanisms inducing corrosion cracking of irradiated austenitic steels and development of a model for prediction of crack initiation N. E. Pirogova, Aki Toivonen, Faiza Sefta, Engineering Failure Analysis Irradiated Austenitic SteelsEngineeringCorrosionMechanical EngineeringDynamic Crack Propagation	2019	14
Irradiation creep of SA 304L and CW 316 stainless steels: Mechanical behaviour and microstructural aspects. Part II: Numerical simulation and test of SIPA model J. Garnier, Yves Bréchet, M. Delnondedieu, Journal of Nuclear Materials Materials ScienceHigh Temperature MaterialsEngineeringSuperalloyCorrosion	2011	13

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