2019 Fall Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 501-2 Nuclear Fuel and the Irradiation Behavior

[2E11-18] Stainless Steel Cladding

Thu. Sep 12, 2019 2:45 PM - 4:55 PM Room E (Common Education Bildg. 2F A23)

Chair:Tatsumi Arima(Kyushu Univ.)

3:45 PM - 4:00 PM

[2E15] R&D of advanced stainless steels for BWR fuel claddings (4)

(5)Investigation of corrosion behavior in nitric acid solution for reprocessing process

*Youko Takahatake1, Hiromu Ambai1, Yuichi Sano1, Masayuki Takeuchi1, Masayuki Watanabe1, Kan Sakamoto2, Shinichiro Yamashita1 (1. JAEA, 2. NFD)

Keywords:Accident tolerant fuel cladding, , fuel cladding, FeCrAl-ODS steels, Spent fuel reprocessing process, Corrosion, Nitric acid solution

The corrosion behavior of FeCrAl-ODS steels for the accident tolerant fuel cladding of LWRs was investigated in nitric acid solution for the reprocessing process of spent fuels. The immersion tests and the electrochemical tests were carried out under gamma ray irradiation. The corrosion of fuel cladding of FeCrAl-ODS steels dose not affected the reprocessing process.