Crack growth rates and fracture toughness of irradiated austenitic stainless steels in BWR environments /

Bibliographic Details
Main Author: Chopra, O. K.
Corporate Authors: Argonne National Laboratory, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research
Other Authors: Shack, W. J.
Format: Government Document eBook
Language:English
Published: [Washington, D.C.] : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, [2008]
Subjects:
Online Access:https://purl.fdlp.gov/GPO/LPS98296
Description
Abstract:In light water reactors, austenitic stainless steels (SSs) are used extensively as structural alloys in reactor core internal components because of their high strength, ductility, and fracture toughness. However, exposure to high levels of neutron irradiation for extended periods degrades the fracture properties of these steels by changing the material microstructure (e.g., radiation hardening) and microchemistry (e.g., radiation-induced segregation). Experimental data are presented on the fracture toughness and crack growth rates (CGRs) of wrought and cast austenitic SSs, including weld heat-affected-zone materials, that were irradiated to fluence levels as high as ≈ 2x 10²¹ n/cm² (E > 1 MeV) (≈ 3 dpa) in a light water reactor at 288-300 C. The results are compared with the data available in the literature. The effects of material composition, irradiation dose, and water chemistry on CGRs under cyclic and stress corrosion cracking conditions were determined. A superposition model was used to represent the cyclic CGRs of austenitic SSs. The effects of neutron irradiation on the fracture toughness of these steels, as well as the effects of material and irradiation conditions and test temperature, have been evaluated. A fracture toughness trend curve that bounds the existing data has been defined. The synergistic effects of thermal and radiation embrittlement of cast austenitic SS internal components have also been evaluated.
Item Description:Title from title screen (viewed July 25, 2008).
"Argonne National Laboratory."
"Date published: March 2008."
"NUREG/CR-6960."
"ANL-06/58."
Physical Description:1 v. (various pagings) : digital, PDF file
Format:Mode of access: Internet from the NRC web site. Address as of 7/25/2008: http://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/cr6960/cr6960.pdf ; current access available via PURL.
Bibliography:Includes bibliographical references (p. 83-88).