2019 Fall Meeting

Presentation information

Oral presentation

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

[2H01-04] Reactor Pressure Vessel

Thu. Sep 12, 2019 10:45 AM - 11:55 AM Room H (Common Education Bildg. 2F B21)

Chair:Katsuhiko Fujii(INSS)

11:30 AM - 11:45 AM

[2H04] FY2018 Investigation for Improvement of Evaluation Method of Irradiation Effects on Reactor Pressure Vessel and Core Internals

(4)Correlation between microstructural changes and yield strength of test reactor irradiated austenitic stainless steels

*Yuichi Miyahara1, Kenji Nishida1, Siwei Chen1 (1. CRIEPI)

Keywords:Austenitic stainless steels, Test reactor irradiation, Atom probe tomography, Transmission electron microscopy, Yield strength

Atom probe and TEM observation were performed on austenitic stainless steels irradiated in a fast reactor and thermal reactor.
It was confirmed that the increment of yield strength can be estimated from microstructure by using the Orowan mechanism. The strength factor of solute enriched clusters was estimated to be about 0.09.