Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide - Kato, Masato; Machida, Masahiko; (ed.) - Prospero Internet Bookshop
Basket (0)
Wishlist (0)
Your personal newsletter
__

Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide
 
Product details:
ISBN13:9781032287171
ISBN10:1032287179
Binding:Paperback
No. of pages:182 pages
Size:234x156 mm
Weight:263 g
Language:English
Illustrations: 59 Illustrations, black & white; 9 Halftones, black & white; 50 Line drawings, black & white; 16 Tables, black & white
785
Category:

Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide

 
Edition number: 1
Publisher: CRC Press
Date of Publication:
 
Normal price:
Publisher's listprice:
GBP 44.99
Estimated price in HUF:
22 769 HUF (21 685 HUF + 5% VAT)
Why estimated?
 
Your price:
20 492 (19 517 HUF + 5% VAT )
discount is: 10% (approx 2 277 HUF off)
The discount is only available for 'Alert of Favourite Topics' newsletter recipients.
Click here to subscribe.
 
Availability:
Estimated delivery time: In stock at the publisher, but not at Prospero's office. Delivery time approx. 3-5 weeks.
Not in stock at Prospero.
Can't you provide more accurate information?
 
Add to basket
  Piece(s)

 
Short description:

Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide offers a deep understanding of MOX properties for nuclear fuels that will be useful for performance evaluation. It also reviews fuel property simulation technology and an irradiation behavior model required for performance evaluation.

Long description:

Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide offers a deep understanding of MOX properties for nuclear fuels that will be useful for performance evaluation. It also reviews fuel property simulation technology and an irradiation behavior model required for performance evaluation.



Based on research findings, the book investigates various physical property data in order to develop MOX fuel for sodium-cooled fast reactors. It discusses a database of MOX properties, including oxygen potential, melting temperature, the lattice parameter, sound speeds, thermal expansion, thermal diffusivity, oxygen self-diffusion, and chemical diffusion coefficients, that was used to derive a science-based model of MOX properties (Sci-M Pro) for fuel-performance code development.



Features:




  • Concisely covers the essential aspects of MOX nuclear fuels.



  • Explores MOX nuclear fuels by systematically evaluating various physical property values using a behavior model.



  • Presents fuel property simulation technology.



  • Considers oxygen potential, the lattice parameter, sound speeds, and oxygen self-diffusion.



  • Discusses melting temperature, thermal expansion, thermal diffusivity, and chemical diffusion coefficients.



The book will be useful for researchers and engineers working in the field of nuclear fuels and nuclear materials.

Table of Contents:
1. Introduction. 2. Experimental Techniques. 3. Properties. 4. Theoretical and Computational Works on Oxide Nuclear-Fuel Materials. 5. Fuel Technologies. 6. Summary. 7. Appendices.