[2C12-16] Radiation Effect 2

[2C15] Data Survey and Trend Analysis of Radiation Effects on Structural Material Properties of Core Internals in Light Water Reactors

(3) IASCC Propagation and Fracture Toughness

*Shigeki Kasahara¹, Koji Fukuya², Yasuhiro Chimi¹, Katsuhiko Fujii², Masato Koshiishi³ (1. JAEA, 2. INSS, 3. NFD)

Keywords:BWR, Core Internals, Stainless Steel, Neutron Irradiation, Crack Propergation, Fracture Toughness

Main objective of this work is to evaluate trend curves of various properties of austenitic stainless steel irradiated with neutrons. Prior to the evaluation, publisued literature survey was carried out and existing data of material properties of irradiated stainless steel were screened in consideration of core conditons of BWR and selected. In this presentation, evaluation about trend curves of IASCC propergation and fracture toughness for BWR core internals will be reported.