2017 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Fuel Cycle and Nuclear Materials » 402-1 Nuclear Materials and the Irradiation Behavior

[2J01-04] Reactor Pressure Vessel Steel

Tue. Mar 28, 2017 10:50 AM - 12:00 PM Room J (16-305 Building No.16)

Chair: Katsuhiko Fujii (INSS)

11:05 AM - 11:20 AM

[2J02] Advanced Management of Irradiation Embrittlement of Reactor Pressure Vessel Steel

(2)Modeling of Nucleation Process of Defect Clusters in RPV Steel during Irradiation

*Kazunori Morishita1, Xiaoyong Ruan1, Toshiki Nakasuji1 (1. Kyoto University)

Keywords:Irradiation Embrittlement, Reactor Pressure Vessel, Multi-scale Modeling, Defect Cluster, Irradiation Correlation

Reactor pressure vessels are known to degraded by irradiation embrittblement during the plant operation, which is attributed by the formation of defect clusters such as copper-rich precipitates in RPV steels during irradiation. In the present study, multiscale modeling is performed to investigate the formation process of the clusters and the formation conditions are clarified. A possibility of developing a new irradiation embrittblement model is discussed. This is one of the series presentations titled by "Advanced Management of Irradiation Embrittlement of Reactor Pressure Vessel Steel".