Open AccessModel Comparison of Passive Compact-Molten Salt Reactor Neutronic Design Using MCNP6 and Serpent-2
Author(s) -
R. Andika Putra Dwijayanto,
Muhammad Rizki Oktavian,
Mahadi Putra,
Andang Widi Harto
Publication year - 2021
Publication title -
atom indonesia
Language(s) - English
Resource type - Journals
eISSN - 2356-5322
pISSN - 0126-1568
DOI - 10.17146/aij.2021.1122
Subject(s) - nuclear engineering , molten salt reactor , blanket , fissile material , monte carlo method , molten salt , breeder reactor , enriched uranium , materials science , neutron , nuclear data , delayed neutron , thorium , nuclear physics , thorium fuel cycle , neutron temperature , nuclear reactor core , prompt neutron , research reactor , control rod , physics , uranium , engineering , mathematics , statistics , metallurgy , composite material