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首页> 美国政府科技报告 >Thermal-Hydraulic Analysis for Core Conversion to the Use of Low-Enriched Uranium Fuels in the KUR
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Thermal-Hydraulic Analysis for Core Conversion to the Use of Low-Enriched Uranium Fuels in the KUR

机译：在KUR中使用低浓铀燃料的岩心转换的热工水力分析

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Thermal-hydraulic analysis was made for LEU fuels in the KUR. Five fuel element geometries are studied. Their dimensions are assumed as combinations of the following parameters, keeping the outer dimensions of element unchanged: meat thickness = 0.50 and 0.61mm, clad thickness = 0.51 and 0.38mm, channel thickness = 2.81 and 2.20mm. Fuel plates are assumed to be either curved or flat and the number of fuel plates ranged from 18 to 22 according to the change in the dimensions. For each fuel element, the relation between the pressure loss and the flow rate, critical heat flux, and heat fluxes for the onset of flow instability and the onset of nucleate boiling are calculated using the computer code PLTEMP3 which has been developed for this study. The effect of fuel material (UAl/sub x/-Al, U sub 3 O sub 8 -Al and U sub 3 Si sub 2 -Al) on the peak fuel temperature is also studied. As a particular interest in the mixed core which may be constructed on the way to the use of LEU fuels, the change in the bypass flow rate due to the change in the gap between different fuel elements is investigated. The results indicate that no significant problem arises due to core conversion for the use of LEU fuels in view of core thermal-hydraulics. With the assumptions used in the analysis and assuming that the permissible minimum margin to ONB be 1.2, the total peaking factor should be lower than 3.3 as far as the primary cooling system is unchanged. (ERA citation 12:013514)

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