Materials for Future Fusion and Fission Technologies
Book Details
Format
Hardback or Cased Book
Book Series
MRS Proceedings
ISBN-10
1605110973
ISBN-13
9781605110974
Publisher
Materials Research Society
Imprint
Materials Research Society
Country of Manufacture
GB
Country of Publication
GB
Publication Date
Jul 30th, 2009
Print length
156 Pages
Weight
350 grams
Dimensions
23.70 x 15.70 x 1.20 cms
Product Classification:
Materials science
Ksh 16,900.00
Manufactured on Demand
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This book highlights nuclear materials issues and challenges on experimental and modeling platforms. Topics include: fundamental defect behavior; experimental and theoretical investigations of radiation damage; behavior of oxide dispersion strengthened steels and other advanced structural materials; corrosion and surface coatings; and modeling and performance of nuclear fuels.
To meet the demands of exponentially growing global energy consumption, extensive research is necessary for future fusion and Generation IV fission reactor power plants; however, structural material performance is a limiting factor. Conventional materials cannot withstand the complex thermomechanical loading, higher operating temperatures, and high irradiation doses. Consequently, research efforts are underway to develop and qualify novel structural materials. Likewise, research on fuel materials seeks to understand and mitigate issues such as oxidation and evolution of the fuel microstructure to high burn-up. To minimize trial-and-error experiments, major fission and fusion materials programs have expanded their use of multiscale materials modeling and simulation. The modeling efforts, in concert with specific experimental validation activities, complement the large experimental programs. This book highlights nuclear materials issues and challenges on experimental and modeling platforms. Topics include: fundamental defect behavior; experimental and theoretical investigations of radiation damage; behavior of oxide dispersion strengthened steels and other advanced structural materials; corrosion and surface coatings; and modeling and performance of nuclear fuels.
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