Abstracts and Available Papers Presented at the 2002 International RERTR Meeting
CHARACTERIZATION
OF BURNED FUEL OF THE TRIGA IPR – R1 RESEARCH REACTOR USING MONTEBURNS CODE
Hugo Moura Dalle1, 3, Robert
Jeraj2 and
Elias B. Tambourgi3
1Centro de Desenvolvimento da Tecnologia Nuclear – CDTN/CNEN
Caixa Postal 941 –
Cidade Universitária – Pampulha
30123-970 – Belo
Horizonte/MG - Brazil
2Jozef Stefan Institute
Jamova 39, 1000
Ljubljana
Ljubljana/Slovenia
3Faculdade de
Engenharia Química - UNICAMP
Cidade Universitária
"Zeferino Vaz"
Caixa Postal 6066 -
CEP 13081-970 – Campinas/SP - Brazil
ABSTRACT
Monteburns is a completely automated
computational tool that links the Monte Carlo code MCNP with the burnup and
decay code Origen2.1. This code system was used to simulate the core of the
CDTN’s TRIGA research reactor and nowadays is the current methodology used for
the theoretical analysis of the main neutronic parameters of such reactor. Some
results of the characterization of the burned fuel elements inside the core
will be presented, including the mass of transuranic elements and of some fission
products, the activity, heatload and radiotoxicities of the fuel. Furthermore,
the core excess reactivity and control rods reactivity worth of the reactor
after the power upgrading to 250 kW as well as the axial and spectral
distribution of the neutron flux in the main irradiation devices were
calculated.