2024 Annual Meeting

Presentation information

Oral presentation

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

[2E08-10] Irradiation Behavior Evaluation, Corrosion

Wed. Mar 27, 2024 11:15 AM - 12:00 PM Room E (21Bildg.3F 21-313)

Chair:Akihiro Suzuki(NFD)

11:30 AM - 11:45 AM

[2E09] Material property evaluation of FeCrAl-ODS steel: Effect of addition of lithium and boron on corrosion

*Chisato Sakaguchi1, Kan Sakamoto1, Yusuke Miura1, Hajime Miyata2, Junji Matsunaga3 (1. NFD, 2. HGNE, 3. GNF-J)

Keywords:light water reactor, ATF, oxide dispersion strengthened alloy, lithium, boron, corrosion

Oxide dispersion strengthened FeCrAl steel (FeCrAl-ODS steel) has ever researched and developed as an accident tolerant fuel cladding material for BWRs. This presentation reports the result of the corrosion behavior of FeCrAl-ODS steel cladding tube in lithium and boron added water which was conducted prior to the fuel irradiation test.