C213 Evaluation of Wastage by Liquid Impingement Droplet Erosion in Steam Generator of Sodium-cooled Fast Reactor

DOI Web Site 1 Citations

Bibliographic Information

Other Title
  • C213 高速炉SGウェステージ評価用液滴衝撃減肉試験(OS8 軽水炉・新型炉・原子力安全)

Description

In a Sodium-cooled Fast Reactor (SFR), liquid sodium is used as heat transfer fluid to carry the energy from the reactor core to the steam generator (SG). In case of a SG tube failure, a defect occurring on a heat transfer tube will cause the high-pressure and high-velocity water/steam to spout onto the low-pressure liquid sodium filling in the space around the tube, to initiate sodium-water reaction. The steam outflow (water, sodium and sodium hydroxide) of the reaction would impinge on neighboring tube to cause erosion/corrosion, which might lead to a secondary failure. In this study, relations between several parameters and erosion rate of Mod.9Cr-1 Mo in anticipated sodium-water reaction conditions were evaluated. The results obtained through the study are as follows; (1) Material with surface coating had better erosion resistance. (2) LDI wastage rate of Mod.9Cr-1 Mo in anticipated conditions was 47.6μ m/s.

Journal

Citations (1)*help

See more

Keywords

Details 詳細情報について

Report a problem

Back to top