2023 Annual Meeting

Presentation information

Oral presentation

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

[3F05-09] Light Water Reactor Materials

Wed. Mar 15, 2023 10:40 AM - 11:55 AM Room F (12 Bildg.3F 1232)

Chair:Kazunori Morishita(Kyoto University)

11:10 AM - 11:25 AM

[3F07] Evaluation of irradiation embrittlement of a harvested reactor pressure vessel material from a domestic PWR plant

(1) Investigation of solute atom cluster formation

*Toru Oumaya1, Terumitsu Miura1, Katsuhiko Fujii1, Koji Fukuya1 (1. Institute of Nuclear Safety System, Incorporated)

Keywords:Reactor pressure vessel, Irradiation embrittlement, Harvested material, Solute atom cluster

Solute atom cluster formation of a harvested RPV material (A533B Cl.1, Cu 0.12wt.%, 2.9×1019 n/cm2) was investigated by 3D atom probe tomography. Cu rich solute atom clusters were observed and its volume fraction was within the data band of domestic surveillance specimen. Comparison with surveillance specimen of the same RPV revealed that both specimen had similar characteristics regarding solute atom cluster formation.