Author : Shijiang Xu
Publisher : Academic Press
ISBN 13 : 9780128126530
Total Pages : 624 pages
Book Rating : 4.1/5 (265 download)
Book Synopsis Graphite and Carbon Materials in Nuclear Engineering by : Shijiang Xu
Download or read book Graphite and Carbon Materials in Nuclear Engineering written by Shijiang Xu and published by Academic Press. This book was released on 2017-09-01 with total page 624 pages. Available in PDF, EPUB and Kindle. Book excerpt: Graphite and Carbon Materials in Nuclear Engineering provides basic knowledge of carbonaceous materials used in High Temperature Reactor (HTR) and Molten Salt Reactor (MSR) systems. The book covers nuclear engineering, working environment and requirements of nuclear graphite; R&D and production of nuclear graphite; irradiation effect (or irradiation damage) of nuclear graphite; and issues the must be resolved for the healthy development of HTR and MSR. This valuable book will serve as a reference book not only for new researchers entering this field from diversified backgrounds, but also for experts including nuclear materials scientists and engineers, particularly those who work in HTR and MSR material section, reactor designers, project managers and governmental nuclear authorities. Provides comprehensive knowledge for people involved in nuclear engineering, especially in R&D of High Temperature Reactor (HTR) and Molten Salt Reactor (MSR) Describes the R&D methodology of carbonaceous materials in nuclear engineering Features material from authors who are internationally known for their expertise in this field and are still active researchers