M. Steinbrück - Concepedia

Author

M. Steinbrück

Also Known As

M Steinbrück, M. Steinbruck, M. Steinbrück, Martin Steinbruck, Martin Steinbrück, Miassoedov, M., Steinbrueck, M., Steinbrück, M., Steinbrück, Martin, Steinbrück, Martin [Hrsg.]

203

Publications

3.7K

Citations

H-Index

Concepts

All Affiliations

Karlsruhe Institute of Technology Paul Scherrer Institute FZI Research Center for Information Technology Institut de Radioprotection et de Sûreté Nucléaire Institute for Atomic Energy Research

About

M. Steinbrück is an author at Karlsruhe Institute of Technology specializing in engineering, materials science, and materials engineering.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	29	51	2.9K
2	Chemical Engineering	17	19	1.1K
3	Chemistry	11	11	521
4	Natural Sciences	5	5	98
5	Applied Physics	5	5	139

M. Steinbrück

Publications

3.4K

Citations

H-Index

Page 1

	Year	Citations
Review on chromium coated zirconium alloy accident tolerant fuel cladding Jianqiao Yang, M. Steinbrück, Chongchong Tang, Journal of Alloys and Compounds Materials EngineeringEngineeringCladding (Metalworking)Materials Science	2021	276
Oxidation kinetics of Cr-coated zirconium alloy: Effect of coating thickness and microstructure Egor Kashkarov, Dmitrii V. Sidelev, M. S. Syrtanov, Corrosion Science Materials EngineeringMaterials ScienceChemical EngineeringOxidation KineticsEngineering	2020	169
High temperature Cr-Zr interaction of two types of Cr-coated Zr alloys in inert gas environment Jianqiao Yang, U. Stegmaier, Chongchong Tang, Journal of Nuclear Materials Materials ScienceMaterials EngineeringEngineeringCr-coated ZrCorrosion	2021	151
Air oxidation of Zircaloy-4, M5® and ZIRLO™ cladding alloys at high temperatures M. Steinbrück, Michael E. Böttcher Journal of Nuclear Materials Materials ScienceMaterials EngineeringAir OxidationHigh Temperature MaterialsEngineering	2011	135
Synopsis and outcome of the QUENCH experimental program M. Steinbrück, M. Große, L. Sepold, Nuclear Engineering and Design Experimental TechnologyExperiment DesignQuench Experimental ProgramOptimal Experimental Design	2010	133
Oxidation of Advanced Zirconium Cladding Alloys in Steam at Temperatures in the Range of 600–1200 °C M. Steinbrück, N. Vér, M. Große Oxidation of Metals Materials EngineeringMaterials ScienceHigh Temperature MaterialsEngineeringOxidation Resistance	2011	125
Prototypical experiments relating to air oxidation of Zircaloy-4 at high temperatures M. Steinbrück Journal of Nuclear Materials Materials ScienceChemical EngineeringAir OxidationEngineeringCorrosion	2009	124
Transient experiments on oxidation and degradation of Cr-coated Zircaloy in steam up to 1600 ℃ Junkai Liu, Chongchong Tang, M. Steinbrück, Corrosion Science Materials ScienceMaterials EngineeringChemical EngineeringTransient ExperimentsCr-coated Zircaloy	2021	103
Systematic investigations on the coating degradation mechanism during the steam oxidation of Cr-coated Zry-4 at 1200 °C Junkai Liu, M. Steinbrück, M. Große, Corrosion Science Materials ScienceMaterials EngineeringChemical EngineeringSystematic InvestigationsEngineering	2022	96
Hydrogen absorption by zirconium alloys at high temperatures M. Steinbrück Journal of Nuclear Materials Materials ScienceEngineeringZirconium AlloysHydrogenHydrogen Embrittlement	2004	91

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