2024 Annual Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 502-1 Nuclear Materials, Degradation, Radiation Effects, and Related Technology

[3C10-13] Corrosion

Thu. Mar 28, 2024 2:45 PM - 3:55 PM Room C (21Bildg.2F 21-205)

Chair:Kazunori Morishita(Kyoto Univ.)

2:45 PM - 3:00 PM

[3C10] Study on corrosion behavior of 316L austenitic steel in Liquid Lead Bismuth Stirred Flow at 1173 K

*Jinkyoung Chung1, Sota Hagiwara1, Masatoshi Kondo1 (1. Tokyo Tech)

Keywords:Lead-bismuth eutectic, Corrosion, 316L austenitic steel, 900℃, Fast reactor, ADS

Liquid lead-bismuth eutectic (LBE) is considered as a coolant of fast reactors, a target material of accelerator drive systems and a coolant of concentrated solar power systems. The liquid LBE systems operated at 1173 K can be applied as a heat source to hydrogen production. Although 316L austenitic steel is a candidate structural material, the corrosion data of 316L steel in flowing LBE at 1173 K is still limited. The liquid metal stirring pot was modified to perform the corrosion test at 1173 K. The corrosion test of 316L steel in stirred LBE was performed at 1173 K for 250 hours. The occurrence of corrosion-erosion was not recognized on the specimen. The specimen showed a mass loss of 5.28 g/m2.

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