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The Syrian Miniature Neutron Source Reactor (MNSR), a 30kW, 89.8% HEU fueled (U-Al), went critical in March, 1996. By operating the reactor at nominal power for 2.5h/day, the estimated core life is 10years. This paper presents the results of fuel burn-up and depletion analysis of the MNSR fuel lattice using the ORIGEN 2 code. A one-group cross-section data base for the ORIGEN 2 computer code was developed...
The calculation of the uranium-235 burn-up in the Syrian Miniature Research Reactor was conducted in this paper using the WIMS-D/4 and CITATION codes. The uranium-235 burn-up was measured experimentally using the measured photoneutron flux in the Be reflector of MNSR subcritical state as well. Good agreements were obtained between the calculated and measured results. The results of the CITATION code...
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