Graphite and Carbon Materials in Nuclear Engineering
- Publisher's listprice EUR 165.00
-
64 449 Ft (61 380 Ft + 5% VAT)
The price is estimated because at the time of ordering we do not know what conversion rates will apply to HUF / product currency when the book arrives. In case HUF is weaker, the price increases slightly, in case HUF is stronger, the price goes lower slightly.
- Discount 10% (cc. 6 445 Ft off)
- Discounted price 58 004 Ft (55 242 Ft + 5% VAT)
Subcribe now and take benefit of a favourable price.
Subscribe
64 449 Ft
Availability
Uncertain availability. Please turn to our customer service.
Why don't you give exact delivery time?
Delivery time is estimated on our previous experiences. We give estimations only, because we order from outside Hungary, and the delivery time mainly depends on how quickly the publisher supplies the book. Faster or slower deliveries both happen, but we do our best to supply as quickly as possible.
Product details:
- Publisher Academic Press
- Date of Publication 1 September 2017
- ISBN 9780128126530
- Binding Paperback
- No. of pages624 pages
- Size 235x191 mm
- Language English 0
Categories
Long 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.
- 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
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
