D.L. Krumwiede - Concepedia

Author

D.L. Krumwiede

University of California, Berkeley ORCID

Also Known As

D. Krumwiede, D. L. Krumwiede, D.L. Krumwiede, David Krumwiede, David L. Krumwiede

Publications

542

Citations

H-Index

Concepts

All Affiliations

University of California, Berkeley Los Alamos National Laboratory Oak Ridge National Laboratory

About

D.L. Krumwiede is an author at University of California, Berkeley specializing in engineering, materials science, and mechanical engineering.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	8	8	516
2	Materials Engineering	3	3	159
3	Applied Physics	1	1	58
4	Chemical Engineering	1	1	56
5	Electrical Engineering	1	1	117

D.L. Krumwiede

Publications

538

Citations

H-Index

Page 1

	Year	Citations
Design Summary of the Mark-I Pebble-Bed, Fluoride Salt–Cooled, High-Temperature Reactor Commercial Power Plant Charalampos Andreades, Anselmo T. Cisneros, Jae Keun Choi, Nuclear Technology EngineeringEnergy EfficiencyReactor DesignMechanical EngineeringReactor Physics	2016	117
Localized mechanical property assessment of SiC/SiC composite materials D. Frazer, M.D. Abad, D.L. Krumwiede, Composites Part A Applied Science and Manufacturing Materials ScienceSic/sic Composite MaterialsEngineeringMechanical PropertiesMechanical Engineering	2014	92
Design and licensing strategies for the fluoride-salt-cooled, high-temperature reactor (FHR) technology Raluca O. Scarlat, Michael Laufer, Edward D. Blandford, Progress in Nuclear Energy Advanced Nuclear ReactorsEngineeringReactor DesignLicensing StrategiesNuclear Reactor Design	2014	79
An analytical method to extract irradiation hardening from nanoindentation hardness-depth curves Anna Kareer, Anya Prasitthipayong, D.L. Krumwiede, Journal of Nuclear Materials Materials ScienceMaterials EngineeringNanoindentation Hardness-depth CurvesEngineeringMaterial Processing	2017	58
Degradation of HT9 under simultaneous ion beam irradiation and liquid metal corrosion D. Frazer, Staffan Qvist, Stephen S. Parker, Journal of Nuclear Materials Materials ScienceChemical EngineeringIon ImplantationEngineeringLiquid Metal Corrosion	2016	56
Direct comparison of nanoindentation and tensile test results on reactor-irradiated materials D.L. Krumwiede, Takuya Yamamoto, Tarik A. Saleh, Journal of Nuclear Materials Materials EngineeringMaterials ScienceEngineeringDirect ComparisonMechanical Engineering	2018	53
Response of 14YWT alloys under neutron irradiation: A complementary study on microstructure and mechanical properties Eda Aydogan, Jordan S. Weaver, U. Carvajal-Nuñez, Acta Materialia Materials ScienceMaterials EngineeringEngineeringMechanical PropertiesMechanical Engineering	2019	48
α′ formation kinetics and radiation induced segregation in neutron irradiated 14YWT nanostructured ferritic alloys Eda Aydogan, Enrique Martínez, Katia March, Scientific Reports	2019	22
Evaluation of the Mechanical Properties of TRISO Particles Using Nanoindentation and Ring Compression Testing D. Frazer, J. Szornel, D.L. Krumwiede, Experimental Mechanics Materials ScienceEngineeringMechanical PropertiesMechanical EngineeringRheology	2017	13

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