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      • KCI등재

        Effect of DUPIC Cycle on CANDU Reactor Safety Parameter

        Nader M.A Mohamed,Alya Badawi 한국원자력학회 2016 Nuclear Engineering and Technology Vol.48 No.5

        Although, the direct use of spent pressurized water reactor (PWR) fuel in CANda Deuterium Uranium (CANDU) reactors (DUPIC) cycle is still under investigation, DUPIC cycle is a promising method for uranium utilization improvement, for reduction of high level nuclear waste, and for high degree of proliferation resistance. This paper focuses on the effect of DUPIC cycle on CANDU reactor safety parameters. MCNP6 was used for lattice cell simulation of a typical 3,411 MWth PWR fueled by UO2 enriched to 4.5w/o U-235 to calculate the spent fuel inventories after a burnup of 51.7 MWd/kgU. The code was also used to simulate the lattice cell of CANDU-6 reactor fueled with spent fuel after its fabrication into the standard 37-element fuel bundle. It is assumed a 5-year cooling time between the spent fuel discharges from the PWR to the loading into the CANDU-6. The simulation was carried out to calculate the burnup and the effect of DUPIC fuel on: (1) the power distribution amongst the fuel elements of the bundle; (2) the coolant void reactivity; and (3) the reactor point-kinetics parameters.

      • SCIESCOPUSKCI등재

        Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide

        Alzamly, Mohamed A.,Aziz, Moustafa,Badawi, Alya A.,Gabal, Hanaa Abou,Gadallah, Abdel Rraouf A. Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.4

        We used MCNP6 computer code to model HTR-10 core reactor. We used two types of fuel; UO<sub>2</sub> and (Th+Pu)O<sub>2</sub> mixture. We determined the critical height at which the reactor approached criticality in both two cases. The neutronic and burnup parameters were investigated. The results indicated that the core fueled with mixed (Th+Pu)O<sub>2</sub>, achieved about 24% higher fuel cycle length than the UO<sub>2</sub> case. It also enhanced safeguard security by burning Pu isotopes. The results were compared with previously published papers and good agreements were found.

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