Daniel M. Wachs - Concepedia

Author

Daniel M. Wachs

Also Known As

D. M. Wachs, D. M. Wachs; I. Glagolenko; F. J. Rice; A. B. Robinson; B. H. Rabin; M. K. Meyer, D. Wachs, D.M. WACHS, D.M. Wachs, DAN WACHS, Dan Wachs, Daniel M Wachs, Daniel M. Wachs, Daniel M. Wachs; Douglas E. Burkes; Steven L. Hayes; Karen Moore; Greg Miller; Gerard Hofman; Yeon Soo Kim

160

Publications

2.1K

Citations

H-Index

Concepts

All Affiliations

Idaho National Laboratory Argonne National Laboratory Korea Atomic Energy Research Institute Belgian Nuclear Research Centre Australian Nuclear Science and Technology Organisation

About

Daniel M. Wachs is an author at Idaho National Laboratory specializing in engineering, materials science, and materials engineering.

Top Concepts

#	Concept	H-Index	Publications	Citations
1	Engineering	20	38	1.3K
2	Applied Physics	9	9	407
3	Chemical Engineering	6	6	136
4	Health Sciences	3	3	102
5	Natural Sciences	1	1	31

Daniel M. Wachs

Publications

1.6K

Citations

H-Index

Page 1

	Year	Citations
IRRADIATION PERFORMANCE OF U-Mo MONOLITHIC FUEL M. K. Meyer, Jian Gan, Jan‐Fong Jue, Nuclear Engineering and Technology	2014	167
Additive manufacturing and mechanical properties of the dense and crack free Zr-modified aluminum alloy 6061 fabricated by the laser-powder bed fusion Abhishek Mehta, Le Zhou, Thinh Huynh, Additive manufacturing Materials ScienceAdvanced Laser ProcessingEngineeringPowder MetallurgyMechanical Properties	2021	163
Transmission electron microscopy characterization of irradiated U–7Mo/Al–2Si dispersion fuel Jian Gan, Dennis D. Keiser, Daniel M. Wachs, Journal of Nuclear Materials Materials ScienceNuclear CeramicEngineeringElectron MicroscopyApplied Physics	2009	112
Fission induced swelling and creep of U–Mo alloy fuel Yeon Soo Kim, G.L. Hofman, Jin-Sik Cheon, Journal of Nuclear Materials Materials EngineeringMaterials ScienceEngineeringAlloy PhaseU–mo Alloy Fuel	2013	88
Microstructural development in irradiated U-7Mo/6061 Al alloy matrix dispersion fuel Dennis D. Keiser, Adam Robinson, Jan‐Fong Jue, Journal of Nuclear Materials Materials ScienceMaterials EngineeringMetal Matrix CompositeEngineeringMechanical Engineering	2009	70
TEM characterization of U–7Mo/Al–2Si dispersion fuel irradiated to intermediate and high fission densities Jian Gan, Dennis D. Keiser, Brandon Miller, Journal of Nuclear Materials Materials ScienceTem CharacterizationNuclear CeramicEngineeringU–7mo/al–2si Dispersion Fuel	2012	69
Neutron Radiography of Irradiated Nuclear Fuel at Idaho National Laboratory Aaron E. Craft, Daniel M. Wachs, Maria A. Okuniewski, Physics Procedia EngineeringNuclear PhysicsNeutron Radiography ReactorNuclear DataRadioactive Contamination	2015	64
Microstructural Development in Inconel 718 Nickel-Based Superalloy Additively Manufactured by Laser Powder Bed Fusion Thinh Huynh, Abhishek Mehta, Kevin Graydon, Metallography Microstructure and Analysis Materials ScienceEngineeringPowder MetallurgyNickel-based SuperalloySuperalloy	2022	57
Swelling of U(Mo)–Al(Si) dispersion fuel under irradiation – Non-destructive analyses of the LEONIDAS E-FUTURE plates S. Van den Berghe, Y. Parthoens, F. Charollais, Journal of Nuclear Materials Dispersion FuelEngineeringApplied PhysicsCosmic RayLeonidas E-future Plates	2012	51
The potential impact of enhanced accident tolerant cladding materials on reactivity initiated accidents in light water reactors Nicholas R. Brown, Aaron Wysocki, Kurt A. Terrani, Annals of Nuclear Energy Materials SciencePotential ImpactChemical EngineeringEnhanced Accident TolerantEngineering	2016	50

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