Graphite and Carbon Materials in Nuclear Engineering

Graphite and Carbon Materials in Nuclear Engineering

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  • 製本 Paperback:紙装版/ペーパーバック版／ページ数 624 p.
  • 言語 ENG
  • 商品コード 9780128126530
  • DDC分類 620

Full Description


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.

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

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