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
Author: 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. ChopraPublisher:
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. JacksonPublisher: 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
Author: ERDA Energy Research Abstracts
Author: Aging, Shaking, and Cracking of Infrastructures
Author: Victor E. SaoumaPublisher: Springer Nature
ISBN: 3030574342
Category : Science
Languages : en
Pages : 1153
Book Description
This self-contained book focuses on the safety assessment of existing structures subjected to multi-hazard scenarios through advanced numerical methods. Whereas the focus is on concrete dams and nuclear containment structures, the presented methodologies can also be applied to other large-scale ones. The authors explains how aging and shaking ultimately lead to cracking, and how these complexities are compounded by their random nature. Nonlinear (static and transient) finite element analysis is hence integrated with both earthquake engineering and probabilistic methods to ultimately derive capacity or fragility curves through a rigorous safety assessment. Expanding its focus beyond design aspects or the state of the practice (i.e., codes), this book is composed of seven sections: Fundamentals: theoretical coverage of solid mechnics, plasticity, fracture mechanics, creep, seismology, dynamic analysis, probability and statistics Damage: that can affect concrete structures, such as cracking of concrete, AAR, chloride ingress, and rebar corrosion, Finite Element: formulation for both linear and nonlinear analysis including stress, heat and fracture mechanics, Engineering Models: for soil/fluid-structure interaction, uncertainty quantification, probablilistic and random finite element analysis, machine learning, performance based earthquake engineering, ground motion intensity measures, seismic hazard analysis, capacity/fragility functions and damage indeces, Applications to dams through potential failure mode analyses, risk-informed decision making, deterministic and probabilistic examples, Applications to nuclear structures through modeling issues, aging management programs, critical review of some analyses, Other applications and case studies: massive RC structures and bridges, detailed assessment of a nuclear containment structure evaluation for license renewal. This book should inspire students, professionals and most importantly regulators to rigorously apply the most up to date scientific methods in the safety assessment of large concrete structures.
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.
Scientific and Technical Aerospace Reports
Author: Paper
Author: Publisher:
ISBN:
Category : Mechanical engineering
Languages : en
Pages : 712
Book Description
ASME Technical Papers
Author: Publisher:
ISBN:
Category : Mechanical engineering
Languages : en
Pages : 816
Book Description