Description
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 correlations- Covers a broad range of micro and nano composite materials for neutron shielding- Discusses recent advances surrounding the synthesis and processing of nanostructures and nanocomposite materials
Table of Contents
1. Introduction to neutron shielding2. Review on neutron absorbing fillers3. Thermoplastic micro- and nanocomposites for neutron shielding 4. Thermosetting micro- and nanocomposites for neutron shielding 5. Elastomeric micro- and nano composites for neutron shielding6. Metal and alloy composites for neutron shielding7. Shielding concrete with neutron attenuating and absorbing components8. Neutron shielding concrete in medical applications9. Advancements in shielding materials for spent fuel storage10. Neutron radiation shielding composites for deep space exploration: An introduction11. Functional characterization of neutron-shielding materials12. Advanced multilayer composite structures for fast neutron detection and shielding protection applications13. Neutron spectroscopy techniques14. Advancements in computational methods for neutron shielding15. Effect of spent nuclear fuel neutron aging on dry cask shielding material
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