2022 Annual Meeting

Presentation information

Oral presentation

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

[2I01-07] Fast Reactor Fuel Development

Thu. Mar 17, 2022 10:00 AM - 12:00 PM Room I

Chair: Masato Kato (JAEA)

11:15 AM - 11:30 AM

[2I06] Suppression of hydrogen permeation from stainless steel cladding tubes loaded with zirconium hydride

*Kenji Konashi1, Satoru Matsuo1, Atsushi Ohuchi2, Toru Higuchi2, Mutsumi Hirai2, Hiroyuki Kazama3 (1. Tohoku Univ., 2. NFD, 3. JAEA)

Keywords:hydride, permeation, sodium, stainless steel, FBR

We investigated the effect of loading Na in the Pellet-Clad tube gap to suppress hydrogen permeation from pins loaded with hydrides.