Open AccessModeling and criticality calculation of the Molten Salt Fast Reactor using Serpent code
Author(s) -
O. Ashraf,
A. D. Smirnov,
G. V. Tikhomirov
Publication year - 2019
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 - 10.1088/1742-6596/1189/1/012007
Subject(s) - fissile material , nuclear engineering , criticality , molten salt , molten salt reactor , actinide , fission products , thorium fuel cycle , fission , breeder reactor , decay heat , environmental science , plutonium , materials science , nuclear physics , engineering , physics , mox fuel , metallurgy , neutron