Open AccessThe Concept of Hybrid Reactor of Tokamak and Molten-salt Thorium Blanket for Producing <sup>233</sup>U out of Neutron Field
Author(s) -
P. N. Alekseev,
É. A. Azizov,
V. N. Dokuka,
G. G. Gladush,
R. R. Hajrutdinov,
С. А. Субботин,
Alexander L. Shimkevich
Publication year - 2015
Publication title -
energy and environmental engineering
Language(s) - English
Resource type - Journals
eISSN - 2331-6306
pISSN - 2331-6330
DOI - 10.13189/eee.2015.030301
Subject(s) - blanket , thorium , molten salt , nuclear engineering , tokamak , molten salt reactor , uranium 233 , radiochemistry , materials science , chemistry , nuclear physics , physics , uranium , thermodynamics , plasma , engineering , mox fuel , composite material
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