Structural Alloys for Nuclear Energy Applications
1st Edition
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Description
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.
Key Features
- 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.
Readership
Nuclear materials researchers at research laboratories, academic institutions, and nuclear waste management and fuel reprocessing organizations
Table of Contents
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
Details
- No. of pages:
- 673
- Language:
- English
- Copyright:
- © Elsevier 2019
- Published:
- 15th August 2019
- Imprint:
- Elsevier
- Hardcover ISBN:
- 9780123970466
- eBook ISBN:
- 9780123973498
About the Editor
Robert Odette
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.
Affiliations and Expertise
Professor Emeritus, University of California at Santa Barbara, Santa Barbara, CA, USA
Steven Zinkle
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 has been a fellow of TMS (2007), AAAS (2007), ANS (2007), ASM International (2003), and the American Ceramic Society (2001).
Affiliations and Expertise
University of Tennessee, Knoxville and Oak Ridge National Laboratory, TN, USA