Open AccessNEUTRONIC CALCULATION FOR PWR MOX FUEL PIN CELLS WITH WIMSD-5B CODE
Author(s) -
Santo Paulus Rajagukguk,
Syaiful Bakhri,
Tukiran Surbakti
Publication year - 2022
Publication title -
urania
Language(s) - English
Resource type - Journals
eISSN - 2528-0473
pISSN - 0852-4777
DOI - 10.17146/urania.2022.28.1.6610
Subject(s) - mox fuel , nuclear engineering , burnup , neutron transport , neutron temperature , physics , neutron , nuclear physics , plutonium , engineering