1 Al-Olayyan, Y., "The Effect of Zircaloy-4 Substrate Surface Condition on the Adhesion Strength and Corrosion of SiC Coatings" 346 (346): 109-119, 2005
2 Wekipedia, "Selective Laser Sintering"
3 Kim, H. C., "Principle and Recent Trend of Rapid Prototyping Technology" 14 (14): 187-199, 2005
4 Brachet, J. C., "Microstructure and Properties of a 3-Layers Nuclear Fuel Cladding Prototype Containing Erbium as a Neutronic Burnable Poison" 2013
5 Nieuwenhove, R. V., "Investigation of the Impact of Coatings on Corrosion and Hydrogen Uptake of Nuclear Components" 2014
6 Lamarsh, J. R., "Introduction to Nuclear Engineering" Prentice-Hall 2012
7 Kim, S. W., "Incore Fuel Management" 44 (44): 2010
8 Hu, X., "Hydrogen Permeation in FeCrAl Alloys for LWR Cladding Application" 461 : 282-291, 2015
9 Kim, H. G., "High-Temperature Oxidation Behavior of Cr-Coated Zirconium Alloy" 842-846, 2013
10 Bragg-Sitton, S., "Development of Advanced Accident-Tolerant Fuels for Commercial LWRs"
1 Al-Olayyan, Y., "The Effect of Zircaloy-4 Substrate Surface Condition on the Adhesion Strength and Corrosion of SiC Coatings" 346 (346): 109-119, 2005
2 Wekipedia, "Selective Laser Sintering"
3 Kim, H. C., "Principle and Recent Trend of Rapid Prototyping Technology" 14 (14): 187-199, 2005
4 Brachet, J. C., "Microstructure and Properties of a 3-Layers Nuclear Fuel Cladding Prototype Containing Erbium as a Neutronic Burnable Poison" 2013
5 Nieuwenhove, R. V., "Investigation of the Impact of Coatings on Corrosion and Hydrogen Uptake of Nuclear Components" 2014
6 Lamarsh, J. R., "Introduction to Nuclear Engineering" Prentice-Hall 2012
7 Kim, S. W., "Incore Fuel Management" 44 (44): 2010
8 Hu, X., "Hydrogen Permeation in FeCrAl Alloys for LWR Cladding Application" 461 : 282-291, 2015
9 Kim, H. G., "High-Temperature Oxidation Behavior of Cr-Coated Zirconium Alloy" 842-846, 2013
10 Bragg-Sitton, S., "Development of Advanced Accident-Tolerant Fuels for Commercial LWRs"
11 Stempien, J. D., "Characteristics of Composite Silicon Carbide Fuel Cladding after Irradiation under Simulated PWR Conditions" 183 (183): 13-29, 2013
12 Idarraga-Trujillo, I., "Assessment at CEA of Coated Nuclear Fuel Cladding for LWRs with Increased Margins in LOCA and Beyond LOCA Conditions" 860-867, 2013
13 Kim, H. G., "Adhesion Property and High-Temperature Oxidation Behavior of Cr-Coated Zircaloy-4Cladding Tube Prepared by 3D Laser Coating" 465 : 531-539, 2015