A key problem in the development of heavy liquid metal cooled reactors is a corrosion of the structural and fuel cladding materials by the coolants. Thus, the problem has been considered as an important design-factor that limits the operational temperature and flow velocity of the next generation nuclear reactors using lead-alloys. Corrosion data has been obtained on as-received and active coating materials of HT9 and 316L in a stagnant lead-alloy containing a reduced atmosphere of oxygen with an exposure time of 1500 hours at 600°C. After each test, the specimens were analyzed metallurgically by using a scanning electron microscopy (SEM) with a energy dispersive X-ray analysis (EDX) for the cross sections of the specimens. In addition, X-ray diffraction (XRD) was performed to evaluate the phase composition of the steels.
Skip Nav Destination
14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4242-8
PROCEEDINGS PAPER
Corrosion Resistance of Active Coating Materials Exposed to Lead-Alloy
Choonho Cho,
Choonho Cho
Korea Atomic Energy Research Institute, Daejeon, Korea
Search for other works by this author on:
Tae-Yung Song,
Tae-Yung Song
Korea Atomic Energy Research Institute, Daejeon, Korea
Search for other works by this author on:
Chungho Cho
Chungho Cho
Korea Atomic Energy Research Institute, Daejeon, Korea
Search for other works by this author on:
Choonho Cho
Korea Atomic Energy Research Institute, Daejeon, Korea
Tae-Yung Song
Korea Atomic Energy Research Institute, Daejeon, Korea
Chungho Cho
Korea Atomic Energy Research Institute, Daejeon, Korea
Paper No:
ICONE14-89486, pp. 563-567; 5 pages
Published Online:
September 17, 2008
Citation
Cho, C, Song, T, & Cho, C. "Corrosion Resistance of Active Coating Materials Exposed to Lead-Alloy." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management. Miami, Florida, USA. July 17–20, 2006. pp. 563-567. ASME. https://doi.org/10.1115/ICONE14-89486
Download citation file:
10
Views
Related Proceedings Papers
Related Articles
European Project “Supercritical Water Reactor-Fuel Qualification Test”: Summary of General Corrosion Tests
ASME J of Nuclear Rad Sci (July,2016)
Properties and Corrosion Resistance of Borided AISI H11 Tool Steel
J. Eng. Mater. Technol (January,2020)
Tribocorrosion Evaluation of AISI 431 Coated With Tungsten Oxynitride
J. Tribol (September,2024)
Related Chapters
Surface Analysis and Tools
Tribology of Mechanical Systems: A Guide to Present and Future Technologies
Zirconium-Steel Bimetallic Tubing for Improved Sour Gas Corrosion Resistance in Oil and Gas Wells
Industrial Applications of Titanium and Zirconium: Fourth Volume
Repair Methods for Loadbearing Steel Structures Operating on the Norwegian Continental Shelf
Ageing and Life Extension of Offshore Facilities