Structural Alloys for Nuclear Energy Applications
Coordonnateurs : Odette Robert, Zinkle Steven
High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk.
Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors? unique personal insight from decades of frontline research, engineering and management.
1. Overview of Structural Materials in Water-Cooled Fission Reactors 2. Overview of Reactor Systems and Operational Environments for Structural Materials in Gen-IV Fission Reactors 3. Overview of Reactor Systems and Operational Environments for Structural Materials in Fusion Reactors 4. Research Tools: Microstructure, Mechanical Properties, and Computational Thermodynamics 5. Radiation and Thermomechanical Degradation Effects in Reactor Structural Alloys 6. Corrosion Issues in Current and Next-Generation Nuclear Reactors 7. Zirconium Alloys for LWR Fuel Cladding and Core Internals 8. Austenitic Stainless Steels 9. Ni-Based Alloys for Reactor Internals and Steam Generator Applications 10. Low-Alloy Steels 11. Ferritic and Tempered Martensitic Steels 12. Nano-Oxide Dispersion-Strengthened Steels 13. Refractory Alloys: Vanadium, Niobium, Molybdenum, Tungsten
Nuclear materials researchers at research laboratories, academic institutions, nuclear waste management and fuel reprocessing organizations
Steven J. Zinkle is Governor’s Chair Professor for Nuclear Materials at the University of Tennessee-Knoxville and Oak Ridge National Laboratory, United States. He has researched the physical metallurgy of structural materials; ion and neutron irradiation effects on the microstructure, physical and mechanical properties of metals and ceramics; fusion and fission reactor materials studies; deformation and fracture mechanisms.
Professor Zinkle has authored or co-authored more than 280 papers and was the inaugural recipient of the Robert Cahn Award, presented at the Elsevier Nuclear Materials Conference (2010), the IEEE Nuclear & Plasma Sciences Society Fusion Technology Award (2006), the Ernest Orlando Lawrence Award (2006), and was appointed ORNL Corporate Fellow in 2004, considered the “highest award possible to an ORNL staff member. He is a member of the US National Academy of Engineering. and
- Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities.
- Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors.
- Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.
Date de parution : 08-2019
Ouvrage de 673 p.
19x23.3 cm
