Technical Meeting on Compatibility Between Coolants and Materials for Fusion Facilities and Advanced Fission Reactors

Surface Modification Methods of Zriconium Alloy fuel cladding Tube for Mitigation of corrosion product deposit in simulated PWR primary coolant

2 Nov 2023, 14:40

20m

M5, Ground Floor, M Building (Vienna, Austria (virtual participation possible))

Compatibility of materials and coolants in nuclear reactors' environment

Speaker

Mr Hee Sang Shim (KAERI)

Presentation materials

3_HShim-f_paper.pdf

3_HShim.pdf