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...

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