Graphite And Carbon Materials In Nuclear Engineering by Shijiang XuGraphite And Carbon Materials In Nuclear Engineering by Shijiang Xu

Graphite And Carbon Materials In Nuclear Engineering

byShijiang Xu, Feiyu Kang, Derek Tsang

Paperback | September 1, 2017

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Graphite and Carbon Materials in Nuclear Engineeringprovides 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
Prof. Xu has worked in nuclear materials field since 1958, took part in building 2MW experimental shield reactor; R&D in nuclear fuel (UO2), graphite for liquid fuel reactors, BeO; in charge of R&D in HTR fuel technology (laboratory scale). Since 1993, Prof. Xu has interested in R&D of nuclear graphite and he has devoted to promote nuc...
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Title:Graphite And Carbon Materials In Nuclear EngineeringFormat:PaperbackDimensions:624 pages, 8.75 × 6.35 × 0.68 inPublished:September 1, 2017Publisher:Academic PressLanguage:English

The following ISBNs are associated with this title:

ISBN - 10:0128126531

ISBN - 13:9780128126530

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Table of Contents

1. Introduction;
2. Basic knowledge of nuclear reactor
3. High temperature reactor
4. Molten salt reactor
5. Structure of carbonaceous materials
6. Production of nuclear graphite
7. Properties of nuclear graphite
8. Radiation effect of nuclear graphite
9. Decommissioning of nuclear graphite
10. Carbonaceous materials in fusion reactor