Crack Initiation Mechanism in Non-ductile Cracking of Irradiated 304L Stainless Steels under BWR Water Environment
スポンサーリンク
概要
- 論文の詳細を見る
The deformation behavior and initiation mechanisms of intergranular (IG) and transgranular (TG) cracks in irradiated 304L stainless steel were studied by slow-strain-rate tensile tests in inert gas and simulated BWR water environments, followed by fractographic and microstructural examinations. Neutron irradiation was made in test reactors to fluences of up to 6.2×1020 n/cm2 (E>1 MeV). Intergranular cracking occurred in water above a critical neutron fluence of around 1×1020 n/cm2, based on the results of the SSRT tests and SEM fractography. That critical fluence is mechanistically supported by irradiated, deformed microstructures exhibiting dislocation channeling at that fluence, while radiation-induced Cr depletion at the grain boundaries was minor. Transgranular cracking of the irradiated material occurred in water below the critical fluence, initiating in the non-uniformly strained surface region of the test bar in the later stages of plastic deformation. The initiation of TG cracking is hypothesized to be related to a high density of deformation twins. Intergranular cracking is proposed to have initiated where localized slip bands terminated at grain boundaries, while TG cracking is inferred to have initiated at deformation twin boundaries. High stress and strain concentrations at grain/twin boundaries would be the common cause of non-ductile crack initiation.
- 社団法人 日本原子力学会の論文
- 2006-08-25
著者
-
Dohi Kenji
Central Research Institute Of Electric Power Industry (criepi)
-
ONCHI Takeo
Central Research Institute of Electric Power Industry (CRIEPI)
-
NAVAS Marta
CIEMAT
-
KARLSEN Wade
VTT Industrial Systems
関連論文
- Crack Initiation Mechanism in Non-ductile Cracking of Irradiated 304L Stainless Steels under BWR Water Environment
- Effects of temperature, strain rate, and specimen orientation on localized plastic deformation of irradiated zircaloy-2.
- Effect of neutron irradiation on fracture behavior of zirconium.
- Yield point phenomenon in neutron irradiated zirconium.
- Effect of neutron irradiation on deformation behavior of zirconium.