Speaker
Mr
Alexey Zhirkin
(Russian Federation)
Description
In this work it is investigated the capabilities of hybrid fusion neutron source (FNS) blankets in reprocessing of spent nuclear fuel and generation of nuclides 233U, 239Pu and tritium. The basic kinds of blankets are considered. There are the blanket with use of heavy water solutions of salts and oxides of uranium and thorium, solid-state and molten salt blanket. The structure and geometrical parameters of blankets, moderator and fertile materials are optimized to obtain the ultimate nuclear fuel yield at the least accumulation of radiation toxic wastes. The neutronics comparative analysis of the different blanket models is presented. In the result, the optimal FNS blanket models are chosen.
| Country or International Organisation | Russian Federation |
|---|---|
| Paper Number | FNS/P7-25 |
Primary author
Mr
Alexey Zhirkin
(Russian Federation)
Co-authors
Boris Chukbar
(Russian Federation)
Dr
Boris Kuteev
(Russian Federation)
Dr
Mikhail Gurevich
(Russian Federation)
