Open AccessPerformance of Thorium Uranium Nitride (Th, U233)N Fuel for 500 MWth GFR Long-Life Without Refuelling use FIITB-CHI Code
Author(s) -
Ratna Dewi Syarifah,
Zaki Su’ud,
Khairul Basar,
Dwi Irwanto
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 - 10.1088/1742-6596/1204/1/012127
Subject(s) - nuclear engineering , thorium fuel cycle , fissile material , thorium , plutonium , mox fuel , nuclear reactor core , uranium , enriched uranium , breeder reactor , neutron transport , liquid fluoride thorium reactor , delayed neutron , natural uranium , neutron flux , environmental science , materials science , neutron , neutron temperature , nuclear physics , physics , engineering