This study has made a calculation of Actinide Minor Addition on Uranium Plutonium Nitride
Fuel for Modular Gas Cooled Fast Reactor. The purpose of this study was to determine the …

Neutronic analysis of UN-PuN fuel use FI-ITB-CHI code for 500MWth GFR longlife without
refuelling has been done. The reactor use fast neutron spectrum, helium coolant and …

Neutronic analysis of comparation UN-PuN fuel and ThN fuel for 300MWth Gas Cooled Fast
Reactor long life without refueling has been done. Gas Cooled Fast Reactor is a Generation …

Nuclear Power Plant can produce electricity more efficiently and have low carbon emissions.
The nuclear reactor used in this study is the MSR (Molten Salt Reactor) FUJI-12. This study …

Comparative study on various thermal powers for gas cooled fast reactor with uranium
plutonium nitride fuel has been done. The purpose of this study was to compare various …

Abstract Comparative Analysis of Hexagonal and Square GFR Fuel Pin Geometry Designs
with Uranium Carbide Fuel has been carried out. Nuclear reactors from Generation I to IV …

Design Study of Gas Cooled Fast Reactor (GFR) with Uranium Plutonium Carbide (UC-PuC) as
Fuel with Addition Protactinium (Pa- 23 Page 1 19 Computational and Experimental Research in …

A study of Neptunium, Americium, and Protactinium addition for GFR 300MWth with Uranium
Carbide fuel has been performed. The purpose of this study was to determine the …

Abstract Performance of Thorium Uranium Nitride Fuel for 500 MWth GFR Long-Life Without
Refueling use FI-ITB-CHI code has been done. Gas Cooled Fast Reactor use fast neutron …