Structural Alloys for Nuclear Energy Applications

Erscheinungsjahr 2019
ISBN: 978-0-12-397046-6
Verlag: William Andrew Publishing

Buch, Englisch, 673 Seiten, Format (B × H): 191 mm x 235 mm, Gewicht: 1520 g

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.

Zielgruppe

<p>Nuclear materials researchers at research laboratories, academic institutions, nuclear waste management and fuel reprocessing organizations </p>

Autoren/Hrsg.

Odette, Robert

Fachgebiete

• Technische Wissenschaften Verfahrenstechnik | Chemieingenieurwesen | Biotechnologie Metallurgie
• Technische Wissenschaften Energietechnik | Elektrotechnik Atomenergietechnik
• Technische Wissenschaften Maschinenbau | Werkstoffkunde Technische Mechanik | Werkstoffkunde Materialwissenschaft: Metallische Werkstoffe

Inhaltsverzeichnis

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

Über Autor(innen)

Odette, Robert
G. Robert Odette is a Distinguished Professor Emeritus of Materials and Mechanical Engineering at UC Santa Barbara, USA. His research focuses on building rigorous models for prediction of material performance in hostile environments, including intense neutron radiation fields in fission and future fusion reactors, as well as developing new high performance, long-lived structural alloys and composites. Research integrates advanced multi-scale models and experiments linking non-equilibrium microstructural evolution, fundamental micromechanics of deformation and fracture, performance sustaining mechanical properties, and structural integrity assessment. Professor Odette has authored or co-authored 240 papers, and has received a number of honors, including the ANS Distinguished achievement award (1994), ANS Mishima Award (1998), the ANS Outstanding Paper award (2004) and TMS Structural Materials Division Scientist of the Year Award. In February 2009 a TMS Symposium was held to celebrate his work on the occasion of his 65th birthday. He is a fellow of ANS, TMS, and ASM.