Abstracts and Available Papers Presented at the 2005 International RERTR Meeting
NEUTRONIC
PARAMETERS OF TAJOURA RESEARCH REACTOR FUELED WITH HEU
and LEU
Omran Abuzid Abulgasem
Faisel Abdula Abuatweirat AbduAlhamed Kh. Ajaj
Renewable Energies and
Water Desalination Research Center
P. O. Box 30878
Tripoli Libya
e-mail [email protected]
ABSTRACT
The computer code WIMSD5B is used to determine the
cross sections of the reactor cells and then CITTATION
diffusion computer code is used to investigate the
neutronic parameters of the IRT-1 Tajoura research
reactor fuelled with High Enriched Uranium (HEU) and Low
Enriched Uranium (LEU). 4-tube and 3-tube of 80%
enrichment, IRT-2M HEU fuel and 8-tube and 6-tube 19.7%
enrichment, IRT-4M LEU fuel cells are studied. This
paper presents the obtained results of the core with
both fuel types. The fresh core calculations show that
fuelling Tajoura reactor core with LEU will increase the
fast neutron flux but decreases the thermal flux
(detailed values are tabulated). The maximum values of
the thermal neutron flux is increased almost three times
using a central neutron trap The core excess reactivity
increases by more than 1% when the core is loaded with
16 fuel assemblies all of 6-tube type and by more than
2% when the core is loaded with 10 fuel assemblies of
6-tube and 6 fuel assemblies of 8-tube type. The core
excess reactivity for HEU is 14.02%,, for the 6-tubes
LEU core it is 15.04%, and for the mixed 6 and 8-tubes
core it is 16.21%.
Contact: Dr. Jordi Roglans-Ribas
Technical Director, RERTR Department
Nuclear Engineering Division – 362
Argonne National Laboratory
9700 South Cass Avenue
Argonne, IL 60439
Fax: +1 630-252-5161
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