Author: United States Government Printing Office
Publisher:
ISBN: 9780160632334
Category :
Languages : en
Pages : 40
Book Description
Role of Time-Dependent Deformation in Intergranular Crack Initiation of Alloy 600 Steam Generator Tubing Material
Author: United States Government Printing Office
Publisher:
ISBN: 9780160632334
Category :
Languages : en
Pages : 40
Book Description
Publisher:
ISBN: 9780160632334
Category :
Languages : en
Pages : 40
Book Description
Chuan Suo Fei Hang
The Role of Time-dependent Deformation in Intergranular Crack Initiation of Alloy 600 Steam Generator Tubing Material
Author: G. S. Was
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 30
Book Description
Publisher:
ISBN:
Category : Nuclear power plants
Languages : en
Pages : 30
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.
Monthly Catalog of United States Government Publications
Author:
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 1154
Book Description
Publisher:
ISBN:
Category : Government publications
Languages : en
Pages : 1154
Book Description
D.R.D.A. Reporter
Author:
Publisher: UM Libraries
ISBN:
Category : Research
Languages : en
Pages : 422
Book Description
Publisher: UM Libraries
ISBN:
Category : Research
Languages : en
Pages : 422
Book Description
Stress Corrosion Crack Detection in Alloy 600 in High Temperature Caustic
Author: Bruce William Brisson
Publisher:
ISBN:
Category :
Languages : en
Pages : 294
Book Description
Alloy 600, the material used for pressurized water reactor steam generator tubing, is susceptible to environmentally assisted stress corrosion cracking. Intergranular stress corrosion cracking (IGSCC) attacks the tubes in areas of high residual stress, and in crevice regions. No method has been successfully developed to monitor steam generator tubing in-situ for crack initiation and growth. Essentially all available published IGSCC crack growth data for alloy 600 is based on non-tubing material. Although it is very likely that the current data base is applicable to tubing processing, differences between tube and other geometries make a comparison between tubing and other data important for verification purposes. However, obtaining crack initiation and growth data from tubing is difficult due to the geometry and the thin wall thickness.
Publisher:
ISBN:
Category :
Languages : en
Pages : 294
Book Description
Alloy 600, the material used for pressurized water reactor steam generator tubing, is susceptible to environmentally assisted stress corrosion cracking. Intergranular stress corrosion cracking (IGSCC) attacks the tubes in areas of high residual stress, and in crevice regions. No method has been successfully developed to monitor steam generator tubing in-situ for crack initiation and growth. Essentially all available published IGSCC crack growth data for alloy 600 is based on non-tubing material. Although it is very likely that the current data base is applicable to tubing processing, differences between tube and other geometries make a comparison between tubing and other data important for verification purposes. However, obtaining crack initiation and growth data from tubing is difficult due to the geometry and the thin wall thickness.
Meeting of Board of Regents
Author: University of Michigan. Board of Regents
Publisher:
ISBN:
Category :
Languages : en
Pages : 404
Book Description
Publisher:
ISBN:
Category :
Languages : en
Pages : 404
Book Description