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Structural Alloys for Nuclear Energy Applications
1st Edition
Editors:
Robert Odette
Steven Zinkle
Hardcover ISBN: 9780123970466
Imprint: Elsevier
Published Date: 1st July 2019
Page Count: 486
Description
From the multi-award winning editorial team of G. Robert Odette (UCSB) and Steve Zinkle (ORNL), and with a contributor board drawn exclusively from the leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications instructs the current and next generations of researchers and industry staff on the behavior of steels and nickel-base alloys for nuclear energy applications. The book covers phenomenon including fatigue, deformation, and embrittlement, as well as materials topics such as advanced ODS steels, RAFM steels for fusion, computational design of nuclear structural materials, and much more.
Distilling valuable archival information for international researchers in the field of radiation effects on structural materials, this full-color reference is a critical resource for graduate students and institutional staff at this time of pivotal change in the nuclear industry.
Key Features
- Edited by multi-award-winning nuclear materials engineers and written by internationally recognized specialists in the subject area.
- Combines sophisticated experimental and computational analysis with critical review, aiding engineers seeking reliable data for in-service usage.
- Interfaces use of steels and nickel-based alloys in current and up and coming applications, providing coverage of the lates research and technological advances.
- Provides an in-depth overview into the latest innovations and research into structural alloys.
Readership
Nuclear materials researchers at research laboratories, academic institutions, nuclear waste management and fuel reprocessing organizations
Table of Contents
1. Overview of structural materials in water-cooled fission reactors
2. Overview of structural materials in Gen-IV fission reactors
3. Overview of reactor systems and operational environments for structural materials in fusion reactors
4. Research tools: Irradiation sources, microstructure, mechanical properties and computational thermodynamics
5. Radiation and thermo-mechanical 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. Nano-oxide dispersion strengthened steels
12. Oxide dispersion strengthened steels
13. Refractory Alloys: Vanadium, Niobium, Molybdenum, Tungsten
Details
- No. of pages:
- 486
- Language:
- English
- Copyright:
- © Elsevier 2019
- Published:
- 1st July 2019
- Imprint:
- Elsevier
- Hardcover ISBN:
- 9780123970466
About the Editor
Robert Odette
G. Robert Odette was most recently Professor of Materials and Professor of Mechanical Engineering UC Santa Barbara, Santa Barbara, CA, USA. Odette’s 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. Odette has authored or co-authored 240 papers. He was winner of the ANS Distinguished achievement award (1994), and is a fellow of ANS (1998). He was past winner of the ANS Mishima Award (1998) & ANS Outstanding paper (2004). In February 2009 a TMS Symposium was held to celebrate his work on the occasion of his 65th birthday.
Affiliations and Expertise
University of California at Santa Barbara, Santa Barbara, CA, USA
Steven Zinkle
Steven J. Zinkle is the Governor’s Chair Professor for Nuclear Materials, University of Tennessee-Knoxville and Oak Ridge National Laboratory in Tennessee. Zinkle 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. He is author or co-author of 230 papers. He was the inaugural recipient of the Robert Cahn Award, Elsevier Nuclear Materials Conference (2010), the IEEE Nuclear & Plasma Sciences Society Fusion Technology Award (2006), and was appointed ORNL Corporate Fellow (2004 – the “highest award possible to an ORNL staff member”), Fellow of TMS (2011), AAAS (2007), ANS (2007), ASM International (2003), American Ceramic Society (2001).
Affiliations and Expertise
University of Tennessee, Knoxville and Oak Ridge National Laboratory, TN, USA
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