H M Chung - Concepedia

Author

H M Chung

Argonne National Laboratory

Also Known As

H Chung, H M Chung, H. Chung, H. M. Chung, H.M Chung, H.M. Chung, Heesun Chung

Publications

858

Citations

H-Index

Concepts

All Affiliations

Argonne National Laboratory

About

H M Chung is an author at Argonne National Laboratory specializing in materials science, engineering, and microstructure.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	10	11	602
2	Materials Science	10	11	602
3	Materials Engineering	6	6	411
4	Applied Physics	2	2	78
5	Natural Sciences	1	1	19

H M Chung

Publications

634

Citations

H-Index

Page 1

	Year	Citations
Development and testing of vanadium alloys for fusion applications H M Chung, B.A. Loomis, Dale Smith Journal of Nuclear Materials Materials EngineeringMaterials ScienceEngineeringVanadium AlloysFusion Power	1996	148
Development of vanadium-base alloys for fusion first-wall—blanket applications Dale Smith, H M Chung, B.A. Loomis, Fusion Engineering and Design Materials ScienceMaterials EngineeringEngineeringVanadium-base AlloysFusion Power	1995	96
Micrograin superplasticity in Zircaloy at 850°C A. M. Garde, H M Chung, T.F. Kassner Acta Metallurgica Materials ScienceEngineeringSuperalloyMicrograin SuperplasticityMicrostructure	1978	70
Effects of neutron irradiation and hydrogen on ductile-brittle transition temperatures of V-Cr-Ti alloys B.A. Loomis, H M Chung, L. J. Nowicki, Journal of Nuclear Materials Materials ScienceMaterials EngineeringEngineeringApplied PhysicsV-cr-ti Alloys	1994	68
Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions Kjell Pettersson, H M Chung, M.C. Billone, Nuclear Waste ManagementNuclear PhysicsEngineeringReactor DesignMechanical Engineering	2009	62
Effect of irradiation damage and helium on swelling and structure of vanadium-base alloys H M Chung, B.A. Loomis, Dale Smith Journal of Nuclear Materials Materials EngineeringMaterials ScienceEngineeringCorrosionMechanical Engineering	1994	51
Properties of V4Cr4Ti for application as fusion reactor structural components H M Chung, B.A. Loomis, Dale Smith Fusion Engineering and Design	1995	32
Microstructural examination of irradiated V–(4–5%)Cr–(4–5%)Ti D.S. Gelles, Philip M. Rice, S.J. Zinkle, Journal of Nuclear Materials Materials ScienceEngineeringMicrostructural ExaminationRadiation Materials ScienceRadiation Exposure	1998	30
Tensile and impact properties of vanadium-base alloys irradiated at <430°C H M Chung, Dale Smith Journal of Nuclear Materials Materials ScienceMaterials EngineeringEngineeringMechanical EngineeringAlloy Design	1998	25
Creep properties of vanadium-base alloys H M Chung, B.A. Loomis, D.L. Smith Journal of Nuclear Materials Materials ScienceMaterials EngineeringEngineeringSevere Plastic DeformationMechanical Engineering	1994	23

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