Open AccessCALCULATION OF FISSILE FUEL PRODUCTION IN SOME MINOR ACTINIDES BASED ON THORIUM
Author(s) -
Mehtap Düz,
Gökmen ŞEKER
Publication year - 2022
Publication title -
euroasia journal of mathematics-engineering naturalandmedical sciences
Language(s) - English
Resource type - Journals
ISSN - 2667-6702
DOI - 10.38065/euroasiaorg.823
Subject(s) - fissile material , nuclear engineering , thorium fuel cycle , actinide , fission , thorium , molten salt , fuel cycle , uranium 233 , spent nuclear fuel , nuclear physics , uranium , mox fuel , materials science , neutron , physics , engineering , metallurgy
In this study, a hybrid reactor with fission fusion reaction was modeled. As a fluid in design; 10% ThC2 + 0.1-1% AmF3 + 89.9-89% Li20Sn80 and 10% ThC2 + 0.1-1% NpF4 + 89.9-89% Li20Sn80 molten salt was used. In the first liquid wall, second liquid wall and shield regions of the reactor, the fissile fuel production was calculated using the MCNPX-2.7.0. ENDF/B-VII.0 nuclear reaction cross section library was used for numerical calculations.