Neutronic Study of Fuel Depletion for the MNSR Research Reactor Using DRAGON5 Code


Citar

Texto integral

Acesso aberto Acesso aberto
Acesso é fechado Acesso está concedido
Acesso é fechado Somente assinantes

Resumo

The aim of this work is to study the fuel depletion of 30 kW miniature neutron source reactor (MNSR). Under operating conditions of two hours per day for five days a week at a peak thermal neutron flux of 1.0E+12 n/cm2 s, the estimated core life is 10 years (200 days). The DRAGON5 code is utilizing to generate the fuel group constants and the infinite multiplication factor versus the MNSR reactor operating time, at different burn-up values. The amounts of uranium burnt up and plutonium produced in the reactor core are calculated using the DRAGON5 transport lattice code. The results are in good agreement with previous studies.

Sobre autores

Jamal Al Zain

Radiations and Nuclear Systems Laboratory; Physics Department

Autor responsável pela correspondência
Email: jalzain@uae.ac.ma
Marrocos, Tetouan; Sana’a

O. El Hajjaji

Radiations and Nuclear Systems Laboratory

Email: jalzain@uae.ac.ma
Marrocos, Tetouan

T. El Bardouni

Radiations and Nuclear Systems Laboratory

Email: jalzain@uae.ac.ma
Marrocos, Tetouan

Arquivos suplementares

Arquivos suplementares
Ação
1. JATS XML

Declaração de direitos autorais © Allerton Press, Inc., 2019