Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Effects of Thermal Aging and Neutron Irradiation on Crack Growth Rate and Fracture Toughness of Cast Stainless Steels and Austenitic Stainless Steel Welds
Effect of Thermal Aging and Neutron Irradiation on Crack Growth Rate and Fracture Toughness of Cast Stainless Steels and Austenitic Stainless Steel Welds
Author: O. K. Chopra
Publisher:
ISBN:
Category : Austenitic stainless steel
Languages : en
Pages : 135
Book Description
Publisher:
ISBN:
Category : Austenitic stainless steel
Languages : en
Pages : 135
Book Description
Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors
Author: John H. Jackson
Publisher: Springer
ISBN: 3030046397
Category : Technology & Engineering
Languages : en
Pages : 2460
Book Description
This two-volume set represents a collection of papers presented at the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The purpose of this conference series is to foster an exchange of ideas about problems and their remedies in water-cooled nuclear power plants of today and the future. Contributions cover problems facing nickel-based alloys, stainless steels, pressure vessel and piping steels, zirconium alloys, and other alloys in water environments of relevance. Components covered include pressure boundary components, reactor vessels and internals, steam generators, fuel cladding, irradiated components, fuel storage containers, and balance of plant components and systems.
Publisher: Springer
ISBN: 3030046397
Category : Technology & Engineering
Languages : en
Pages : 2460
Book Description
This two-volume set represents a collection of papers presented at the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The purpose of this conference series is to foster an exchange of ideas about problems and their remedies in water-cooled nuclear power plants of today and the future. Contributions cover problems facing nickel-based alloys, stainless steels, pressure vessel and piping steels, zirconium alloys, and other alloys in water environments of relevance. Components covered include pressure boundary components, reactor vessels and internals, steam generators, fuel cladding, irradiated components, fuel storage containers, and balance of plant components and systems.
Energy Research Abstracts
ERDA Energy Research Abstracts
Paper
Author:
Publisher:
ISBN:
Category : Mechanical engineering
Languages : en
Pages : 712
Book Description
Publisher:
ISBN:
Category : Mechanical engineering
Languages : en
Pages : 712
Book Description
Scientific and Technical Aerospace Reports
Crack Growth Rates and Fracture Toughness of Irradiated Austenitic Stainless Steels in BWR Environments
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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 (almost equal to) 2x 1021 n/cm2 (E> 1 MeV) ((almost equal to) 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.
Publisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
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 (almost equal to) 2x 1021 n/cm2 (E> 1 MeV) ((almost equal to) 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.
ASME Technical Papers
Author:
Publisher:
ISBN:
Category : Mechanical engineering
Languages : en
Pages : 816
Book Description
Publisher:
ISBN:
Category : Mechanical engineering
Languages : en
Pages : 816
Book Description
ASM Handbook
Author: ASM International. Handbook Committee
Publisher:
ISBN:
Category : Fracture mechanics
Languages : en
Pages : 1080
Book Description
These volumes cover the properties, processing, and applications of metals and nonmetallic engineering materials. They are designed to provide the authoritative information and data necessary for the appropriate selection of materials to meet critical design and performance criteria.
Publisher:
ISBN:
Category : Fracture mechanics
Languages : en
Pages : 1080
Book Description
These volumes cover the properties, processing, and applications of metals and nonmetallic engineering materials. They are designed to provide the authoritative information and data necessary for the appropriate selection of materials to meet critical design and performance criteria.