Preface Acknowledgments 1. Introduction 2. Dispersion principles 3. Unbounded isotropic and anisotropic media 4. Reflection and refraction 5. Oblique incidence 6. Waves in plates 7. Surface and subsurface waves 8. Finite element method for guided wave mechanics 9. The semi-analytical finite element method (SAFE) 10. Guided waves in hollow cylinders 11. Circumferential guided waves 12. Guided waves in layered structures 13. Source influence on guided wave excitation 14. Horizontal shear 15. Guided waves in anisotropic media 16. Guided wave phased arrays in piping 17. Guided waves in viscoelastic media 18. Ultrasonic vibrations 19. Guided wave array transducers 20. Introduction to guided wave nonlinear methods 21. Guided wave imaging methods Appendix A: ultrasonic nondestructive testing principles, analysis and display technology Appendix B: basic formulas and concepts in the theory of elasticity Appendix C: physically based signal processing concepts for guided waves Appendix D: guided wave mode and frequency selection tips.

Ultrasonic Guided Waves in Solid Media

At moderately high temperature sections of Advanced Ultra Super Critical (AUSC) boilers, welding of superalloys to austenitic steels is inevitable owing to economic aspects of boiler. Welding of SUS 304H and Inconel 617 (IN 617) was attempted using IN 617 filler material employing conventional Gas Tungsten Arc Welding (GTAW) process and the procedure was successfully established along with optimized welding parameters. Microstructural characterization was carried out to identify various zones on either side of the fusion boundaries. Unmixed Zone and Heat Affected Zone (HAZ) were observed towards SUS 304H fusion boundary while no distinct HAZ was observed towards IN 617 fusion boundary. Micro-hardness profiling indicated decrease in hardness at the HAZ towards SUS 304H fusion boundary. Mechanical properties evaluation at both ambient and elevated temperatures was carried out and data obtained was compared with those of base metals. The tensile strength of the cross weld specimens at high temperatures were observed to be marginally lower than that of IN 617 but significantly more than that of SUS 304H, hence, tolerable. Stress-rupture properties of the cross-weld specimens as tested in this study were found to be intermediate to the base metals’ data, thus, suitable for AUSC power plants' boiler applications. Hence, this work gives an insight into welding procedure establishment, microstructural development, variation of mechanical properties at elevated temperatures and stress-rupture properties of the dissimilar metal welds at elevated temperatures.

Development and evaluation of SUS 304H — IN 617 welds for advanced ultra supercritical boiler applications

The fluoride-salt-cooled high-temperature reactor (FHR) is a Generation IV nuclear energy system with huge potential for further development. Owing to its unique advantages, such as inherent safety, high economical potential, small modular design, environmental adaptability, and nonproliferation, FHRs have been the focus of considerable attention. In this study, the history and characteristics of FHR are reviewed first, including the concept initiation and active exploration stages. Then, the research status of FHR is introduced, which is about the state of the art in primary coolant systems, structural materials, key equipment, energy conversion systems, direct reactor auxiliary cooling systems, nuclear fuel, tritium control strategies, and experimental studies. Furthermore, the challenges faced by FHR technology are summarized, including corrosion of structural materials, optimization of energy conversion systems, solidification of fluoride salts, control of tritium, control of beryllium contamination, enrichment of lithium fluoride-beryllium fluoride salt, design of core refueling, and operation and control of pebble bed reactor. Based on the above, the focuses of research on FHR design are discussed, and areas of study for future development of FHR technology are recommended. This paper aims to provide a reference for the research and development of FHR in the future. 

Fluoride-salt-cooled high-temperature reactors: Review of historical milestones, research status, challenges, and outlook

Current energy drivers are pushing research in power generation materials towards improved efficiency and improved environmental impact. In the context of new generation ultra-supercritical (USC) power plant, this is represented by increased efficiency, service temperature reaching 750 °C, pressures in the range of 35–37.5 MPa and associated carbon capture technology. Ni base alloys are primary candidate materials for long term high temperature applications such as boilers. The transition from their current applications, which have required lower exposure times and milder corrosive environments, requires the investigation of their microstructural evolution as a function of thermo-mechanical treatment and simulated service conditions, coupled with modelling activities that are able to forecast such microstructural changes. The lack of widespread microstructural data in this context for most nickel base alloys makes this type of investigation necessary and novel. Alloy INCONEL 617 is one of the Ni-base candidate materials. The microstructures of four specimens of this material crept at temperatures in the 650–750 °C range for up to 20,000 h have been characterised and quantified. Grain structure, precipitate type and location, precipitate volume fraction, size and inter-particle spacing have been determined. The data obtained are used both as input for and validation of a microstructurally-based CDM model for forecasting creep properties.

/pdf/characterisation-of-microstructure-and-creep-properties-of-4vmq0z762f.pdf

Characterisation of microstructure and creep properties of alloy 617 for high-temperature applications

the aim of this article is to evaluate the mechanical and microstructure properties of Inconel 617 weldments produced by direct current electrode negative (DCEN) gas tungsten arc welding (GTAW) and pulse current GTAW. In this regard, the micro structural examinations, impact test and hardness test were performed. The results indicated that the joints produced by direct mode GTAW exhibit poor mechanical properties due to presence of coarse grains and dendrites. Grain refining in pulse current GTAW is reason of higher toughness and impact energy than DCEN GTAW. Further investigations showed that the epitaxial growth is existed in both modes that can strongly affect the mechanical behavior of the joints in heat affected zone (HAZ).

https://www.mop.ir/portal/File/ShowFile.aspx?ID=8a4c62a5-c813-42b4-835a-642d16f7bf91

A Comparative Study on Direct and Pulsed Current Gas Tungsten Arc Welding of Alloy 617

https://oatao.univ-toulouse.fr/4705/1/Chomette_4705.pdf

Creep behaviour of as received, aged and cold worked INCONEL 617 at 850 °C and 950 °C

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Creep behaviour of as received, aged and cold worked INCONEL 617 at 850 °C and 950 °C