Data survey and trend analysis of radiation effects on structural material properties of core internals in light water reactors, 1; Overview

Chimi, Yasuhiro; Fukuya, Koji*; Kasahara, Shigeki; Fujii, Katsuhiko*; Hanawa, Satoshi 

To contribute to materials degradation assessment in core internals of light water reactors, we have widely surveyed the literature on irradiation properties of austenitic stainless steels (SSs) and summarized the data. In the present investigation, in terms of mechanical properties (tensile properties, hardness, and fracture toughness), IASCC properties (IASCC susceptibility, IASCC initiation, and IASCC growth), stress relaxation - creep - swelling, and microstructural properties (microstructures and grain boundary segregation) in irradiated SSs, we have collected the data and made the spread sheets separately on PWR and BWR according to the test conditions and the target materials. We have also considered the trend curves on the mechanical properties, the IASCC properties, etc. based on the knowledge obtained through surveying the literature on dose dependence of the irradiation properties. In the presentation, we will report the overview of the present investigation.