The results of the studies directed to the determination of neutron-physical and radiation characteristics of promising nuclear fuel compositions are presented. The features of handling of modified irradiated nuclear fuel of a thermal reactor in dry storage systems are considered. The necessity of correcting nuclear constants used in calculations of the multiplying lattice criticality and storage systems with thorium is shown.
- dry storage
- promising ceramic nuclear fuel
- threshold reactions in nuclear fuel
ASJC Scopus subject areas
- Physics and Astronomy(all)