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Design of Small Gas Cooled Fast Reactor with Two Region of Natural Uranium Fuel Fraction

机译:用两种天然铀燃料分数设计小型气体冷却快速反应器

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A design study of small Gas Cooled Fast Reactor with two region fuel has been performed. In this study, design GCFR with Helium coolant which can be continuously operated by supplying mixed Natural Uranium without fuel enrichment plant or fuel reprocessing plant. The active reactor cores are divided into two region fuel i.e. 60% fuel fraction of Natural Uranium as inner core and 65% fuel fraction of Natural Uranium as outer core. Each fuel core regions are subdivided into ten parts (region-1 until region-10) with the same volume in the axial direction. The fresh Natural Uranium initially put in region-1, after one cycle of 10 years of burn-up it is shifted to region-2 and the each region-1 filled by fresh Natural Uranium. This concept is basically applied to all regions in both cores area, i.e. shifted the core of i~(th) region into i+1 region after the end of 10 years burn-up cycle. For the next cycles, we will add only Natural Uranium on each region-1. The burn-up calculation is performed using collision probability method PIJ (cell bum-up calculation) in SRAC code which then given eight energy group macroscopic cross section data to be used in two dimensional R-Z geometry multi groups diffusion calculation in CITATION code. This reactor can results power thermal 600 MWth with average power density i.e. 80 watt/cc. After reactor start-up the operation, furthermore reactor only needs Natural Uranium supply for continue operation along 100 years. This calculation result then compared with one region fuel design i.e. 60% and 65% fuel fraction. This core design with two region fuel fraction can be an option for fuel optimization.
机译:已经进行冷快堆有两个区域燃料的小型气的设计研究。在这项研究中,设计与GCFR氦冷却液可以通过无燃料浓缩厂或燃料后处理厂提供混合天然铀连续运转。活性反应堆堆芯被分成两个区域,即燃料天然铀的60%的燃料馏分作为内芯和天然铀为外芯的65%的燃料馏分。每个燃料芯区域被细分成10份(区域1,直到区域-10)在轴向方向上具有相同的体积。新鲜的天然铀初步建成区域-1,10年燃耗的一个周期后,被转移到区域2和每个区域-1由新鲜天然铀填补。这个概念是基本上适用于所有的区域中两个核心区域,即移动芯的i〜(th)的区域划分成i + 1个的区域10年燃耗周期结束之后。对于下一个周期,我们将在每个区域-1只添加天然铀。燃尽计算在SRAC代码,然后给定8个能量组宏观截面数据在二维R-Z的几何形状的多组扩散计算中使用在现有的代码中使用的冲突概率的方法PIJ(细胞烧伤式计算)进行。此反应器可以结果功率热大气与平均功率密度即80瓦特/立方厘米。反应器启动后的操作,而且反应器只需要为继续沿着成立100周年天然铀供应。该计算结果再与一个区域的燃料设计即60%和65%的燃料分数进行比较。这个核心设计有两个地区的燃油消耗率可为燃料优化的选项。

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