%A Vu, Thanh Mai
%A Hartanto, Donny
%D 2020
%T Comparison of Deterministic and Stochastic Depletions in Graphite-Filled MOX Fuel Assembly Design
%K
%X A comparison between stochastic and deterministic depletion calculations based on a graphite-filled MOX fuel assembly configuration is presented in this paper. The infinite multiplication factors and isotope inventory changes as a function of burnup obtained by Monte Carlo method module SCALE/KENO and deterministic method module SCALE/NEWT are compared with those obtained by deterministic code HELIOS. The impact in calculation results by using different nuclear data library is also investigated. The SCALE/KENO results show a good agreement with SCALE/NEWT results in the eigenvalue as a function of burnup (less than 0.1%). However, the absolute difference in the initial k ¥ between SCALE/KENO and NEWT modules and HELIOS results is quite large (around 1.1%) and the isotope inventory changes show quite differently at the end of cycle. The uranium and plutonium depletion rates calculated by SCALE/KENO and SCALE/NEWT have quite good agreement. By using the same data library, the good agreement between stochastic and deterministic code’s results were confirmed.
%U https://js.vnu.edu.vn/MaP/article/view/4499
%J VNU Journal of Science: Mathematics - Physics
%0 Journal Article
%R 10.25073/2588-1124/vnumap.4499
%V 36
%N 4
%@ 2588-1124
%8 2020-10-07