Graphite and Carbon Materials in Nuclear Engineering

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 engineeringFeatures material from authors who are internationally known for their expertise in this field and are still active researchers INDICE: 1. Introduction;2. Basic knowledge of nuclear reactor3. High temperature reactor4. Molten salt reactor5. Structure of carbonaceous materials6. Production of nuclear graphite7. Properties of nuclear graphite8. Radiation effect of nuclear graphite9. Decommissioning of nuclear graphite10. Carbonaceous materials in fusion reactor

• ISBN: 978-0-12-812653-0
• Editorial: Academic Press
• Encuadernacion: Rústica
• Páginas: 624
• Fecha Publicación: 01/09/2017
• Nº Volúmenes: 1
• Idioma: Inglés