Micro and Nanostructured Composite Materials for Neutron Shielding Applications

Micro- and Nanostructured Composite Materials for Neutron Shielding Applications presents recent developments and future possibilities for neutron shielding materials. Emphasis is placed on the correlation between the morphology, shielding mechanisms, and other desired properties, including their mechanical and thermal properties. The effect of neutron absorbing fillers, including their size on final properties is also examined, as are recent advancements in preparation, characterization and simulation techniques. Written by specialists in their respective fields, this comprehensive resource will help professionals and students understand the fundamentals of neutron shielding, as well as the properties of micro- and nanopolymer-based composites, concrete materials, alloy materials and metal-ceramic composites.

Provides an up-to-date understanding of the fundamentals of shielding mechanisms, morphology and material property correlationsCovers a broad range of micro and nano composite materials for neutron shieldingDiscusses recent advances surrounding the synthesis and processing of nanostructures and nanocomposite materials

1. Introduction to neutron shielding
2. Review on neutron absorbing fillers
3. Thermoplastic micro- and nanocomposites for neutron shielding
4. Thermosetting micro- and nanocomposites for neutron shielding
5. Elastomeric micro- and nano composites for neutron shielding
6. Metal and alloy composites for neutron shielding
7. Shielding concrete with neutron attenuating and absorbing components
8. Neutron shielding concrete in medical applications
9. Advancements in shielding materials for spent fuel storage
10. Neutron radiation shielding composites for deep space exploration: An introduction
11. Functional characterization of neutron-shielding materials
12. Advanced multilayer composite structures for fast neutron detection and shielding protection applications
13. Neutron spectroscopy techniques
14. Advancements in computational methods for neutron shielding
15. Effect of spent nuclear fuel neutron aging on dry cask shielding material