Neutronics Calculations of Performance Enhancement of the Lithium-Uranium Blanket of a Tokamak Reactor

The possibility of using a tokamak as a DT-fusion reactor source of fast neutrons for irradiating waste uranium in order to produce energy and fissile fuel ( 239 Pu) for fission reactors, and tritium with breeding ratio ≥1.15 is considered. Models with variable uranium, lithium, and lead content ove...

Full description

Saved in:
Bibliographic Details
Published in:Atomic energy (New York, N.Y.) N.Y.), 2021-10, Vol.130 (6), p.319-322
Main Authors: Gladush, G. G., Mirnov, S. V., Lopatkin, A. V., Lukasevich, I. B.
Format: Article
Language:English
Subjects:
Fusion reactors
Hadrons
Heavy Ions
Nuclear Chemistry
Nuclear Energy
Nuclear Physics
Physics
Physics and Astronomy
Uranium
Citations: Items that this one cites
Items that cite this one
Online Access:Get full text
Tags: Add Tag
No Tags, Be the first to tag this record!
Description
Summary:The possibility of using a tokamak as a DT-fusion reactor source of fast neutrons for irradiating waste uranium in order to produce energy and fissile fuel ( 239 Pu) for fission reactors, and tritium with breeding ratio ≥1.15 is considered. Models with variable uranium, lithium, and lead content over the thickness of the blanket are considered in order to determine the increase in its productivity. Compared to a uniform distribution of the raw material, variants with non-uniform loading over thickness afford almost a two-fold increase in plutonium production.
ISSN:1063-4258
1573-8205
DOI:10.1007/s10512-022-00817-z