Graphite and Carbon Materials in Nuclear Engineering

By Shijiang Xu, Feiyu Kang, Derek Tsang, et al.

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.

• Format: Paperback
• Language: English
• ISBN: 0128126531
• ISBN13: 9780128126530
• Release Date: January 2029
• Publisher: Academic Press
• Length: 624 Pages