Robert J. Comstock - Concepedia

Author

Robert J. Comstock

Westinghouse Electric (United States)

Also Known As

José Júlio Pinheiro dos Santos Júnior, Robert Comstock, Robert J Comstock, Robert J. Comstock, Robert L. Dressler

Publications

2.3K

Citations

H-Index

Concepts

All Affiliations

Westinghouse Electric (United States)Pennsylvania State University Nippon Steel (Japan)British Steel (United Kingdom)China Steel (Taiwan)

About

Robert J. Comstock is an author at Westinghouse Electric (United States) specializing in engineering, materials science, and corrosion.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	12	12	2K
2	Chemical Engineering	4	4	912
3	Applied Physics	3	3	575
4	Materials Engineering	2	2	195
5	Chemistry	1	1	480

Robert J. Comstock

Publications

2.2K

Citations

H-Index

Page 1

	Year	Citations
Corrosion of Zirconium Alloys Used for Nuclear Fuel Cladding Arthur T. Motta, Adrien Couet, Robert J. Comstock Annual Review of Materials Research Materials ScienceCorrosion TechnologyChemical EngineeringNuclear Fuel RodsEngineering	2015	480
Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: relation to corrosion rate Aylin Yilmazbayhan, Arthur T. Motta, Robert J. Comstock, Journal of Nuclear Materials Materials ScienceEngineeringCorrosionCorrosion RateSurface Science	2003	276
Transmission electron microscopy examination of oxide layers formed on Zr alloys Aylin Yilmazbayhan, E. Breval, Arthur T. Motta, Journal of Nuclear Materials Materials ScienceEngineeringZr AlloysElectron MicroscopyOxide Electronics	2006	271
Deformation-induced phase transformation and strain hardening in type 304 austenitic stainless steel A. K. De, John G. Speer, David K. Matlock, Metallurgical and Materials Transactions A Materials ScienceEngineeringSevere Plastic DeformationDeformation-induced Phase TransformationHigh Strength Low Alloy Steel	2006	244
Multilayer (TiN, TiAlN) ceramic coatings for nuclear fuel cladding Ece Alat, Arthur T. Motta, Robert J. Comstock, Journal of Nuclear Materials Materials ScienceNuclear CeramicEngineeringNuclear Fuel CladdingThermal Barrier Coating	2016	208
Zirconium alloys for supercritical water reactor applications: Challenges and possibilities Arthur T. Motta, Aylin Yilmazbayhan, Marcelo José Gomes da Silva, Journal of Nuclear Materials Materials ScienceMaterials EngineeringChemical EngineeringEngineeringCorrosion	2007	159
Hydrogen pickup measurements in zirconium alloys: Relation to oxidation kinetics Adrien Couet, Arthur T. Motta, Robert J. Comstock Journal of Nuclear Materials Materials ScienceChemical EngineeringEngineeringHydrogen TransitionCorrosion	2014	144
Ceramic coating for corrosion (c3) resistance of nuclear fuel cladding Ece Alat, Arthur T. Motta, Robert J. Comstock, Surface and Coatings Technology Materials ScienceChemical EngineeringCorrosion ProtectionEngineeringCorrosion	2015	129
Corrosion of ferritic–martensitic steels in steam and supercritical water Jérémy Bischoff, Arthur T. Motta, Chad M. Eichfeld, Journal of Nuclear Materials Ferritic–martensitic SteelsCorrosion ResistanceCorrosion	2012	110
Evolution of the oxide structure of 9CrODS steel exposed to supercritical water Jérémy Bischoff, Arthur T. Motta, Robert J. Comstock Journal of Nuclear Materials Materials ScienceMaterials EngineeringEngineeringMechanical EngineeringOxide Structure	2009	36

Page 1