2017 Fall Meeting

Presentation information

Oral presentation

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

[2I01-07] Stainless Steel

Thu. Sep 14, 2017 10:05 AM - 12:00 PM Room I (C310 - C Block)

Chair:Terumitsu Miura (INSS)

10:35 AM - 10:50 AM

[2I03] FY2016 investigation for improvement of evaluation methods of irradiation effects on reactor pressure vessel and core internals

(3)Characterization of microstructural change on neutron irradiated type 316L stainless steel

*Yuichi Miyahara1, Kenji Nishida1, Siwei Chen1, Katsuhiko Fujii2, Yuji Kitsunai3 (1. CRIEPI, 2. INSS, 3. NFD)

Keywords:Type 316L stainless steel, Neutron irradiation, Atom probe tomography, Solute cluster

The microstructure formed by neutron irradiation was evaluated by atom prove tomography (APT) and transmission electron microscopy (TEM) observation for type 316L stainless steels with different neutron irradiation dose.
In APT analyses, nickel and silicon enriched solute clusters were observed, and black dots and dislocation loops were observed by TEM observation.
Based onthe Orowan mechanism, estimated yield strength increase was in good agreement with the measured value by assuming the strength factor of the solute cluster to be constant.