Open Access
Simulations of fusion neutron source based on the axially symmetric mirror trap for the thorium hybrid reactor
Author(s) -
V. V. Prikhodko,
А. В. Аржанников
Publication year - 2020
Publication title -
journal of physics. conference series
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.21
H-Index - 85
eISSN - 1742-6596
pISSN - 1742-6588
DOI - 10.1088/1742-6596/1647/1/012004
Subject(s) - axial symmetry , deuterium , neutron , neutron source , yield (engineering) , tritium , plasma , fusion power , nuclear physics , nuclear engineering , trap (plumbing) , nuclear fusion , materials science , physics , quantum mechanics , meteorology , engineering , metallurgy
The axially symmetric open mirror trap is considered as a neutron source for the hybrid thorium reactor. Plasma parameters are optimized in order to achieve the maximum neutron yield in the volume surrounded by the subcritical fuel assembly while meeting the stability criteria. For plasma consisting of equal amounts of deuterium and tritium isotopes, in the fuel assembly region, the neutron yield was found to be 0.6 × 10 17 n/s at an input power of 20 MW, and it will increase to 2.6 × 10 17 n/s if the input power increases two times. In optimal regimes, the plasma parameters were close to those achieved in experiments at the GDT facility.