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Materials for Future Fusion and Fission Technologies
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Materials for Future Fusion and Fission Technologies

Book Details

Format Paperback / Softback
Book Series MRS Proceedings
ISBN-10 110740844X
ISBN-13 9781107408449
Publisher Cambridge University Press
Imprint Cambridge University Press
Country of Manufacture GB
Country of Publication GB
Publication Date Jun 5th, 2014
Print length 156 Pages
Weight 22 grams
Dimensions 22.90 x 15.20 x 0.80 cms
Product Classification: Materials science
Ksh 5,050.00
Manufactured on Demand 0 in stock

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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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