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Neutronics Modeling and Analysis of the TMSR-SF1 Core with Explicitly Described Fuel Pebble Loadings

机译:带有明确描述的燃料卵石载荷的TMSR-SF1堆芯的中子学建模与分析

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The growing global demand for emission-free energy is creating a market for advanced Generation-IV NPP, and the Fluoride salt-cooled High-temperature Reactor design with a pebble-type fuel is a promising candidate. However, this design also brings unique challenges, namely evaluating the effects of the fuel's distribution and dynamic movement. Generating explicitly described fuel pebble loading patterns is non-trivial. This study serves two main purposes: I) to investigate the neutronic performance of pebble type fuel within the TMSR-SF1, and 2) to conduct a preliminary comparison between pebble coordinate generation methods. The first method of coordinate generation, the Discrete Element Method (DEM), is a particle-tracking model which accounts for inter-particle forces. While this method generates packing distributions closer to real-world scenarios, it is computationally intense. The alternative method analyzed is a mathematical model (MM), which fills arbitrary domains through simple geometric rules on the addition of particles. This method, while less realistic, generates coordinates significantly faster. Afterwards, fuel pebble coordinates from both methods are utilized to generate inputs for high-fidelity neutronics modelling. The results of these simulations, with the aid of various tools within Python, allowed for the neutronic analysis of the core, specifically when considering the eigenvalues of each coordinate set, and the fission power distribution within the fuel pebbles. It was found that the packing fraction in the axial direction to be consistent within the MM coordinate generation method, and the general trends similar between it and DEM-generated coordinates. Additionally, the eigenvalues of the simulated core were found to be proportional to the number of pebbles within the core. Finally, the fission power distribution of the cores was found to be qualitatively consistent both within many sets of MM-generated coordinates, and in comparisons of the two coordinate generation methods.
机译:全球对无排放能源的日益增长的需求为先进的IV代NPP创造了市场,并且采用卵石型燃料的氟化物盐冷高温反应堆设计是一个有前途的候选人。然而,这种设计也带来了独特的挑战,即评估燃料分布和动态运动的影响。生成明确描述的燃料卵石装载模式并非易事。这项研究有两个主要目的:I)研究TMSR-SF1中卵石型燃料的中子性能,以及2)对卵石坐标生成方法之间进行初步比较。坐标生成的第一种方法是离散元素方法(DEM),它是一种粒子跟踪模型,它考虑了粒子间的力。尽管此方法生成的填充分布更接近实际情况,但计算强度很高。分析的另一种方法是数学模型(MM),该模型通过添加粒子的简单几何规则填充任意域。这种方法虽然不太现实,但生成坐标的速度明显更快。然后,利用两种方法的燃料卵石坐标生成输入,以进行高保真中子学建模。这些模拟的结果借助Python中的各种工具,可以对堆芯进行中子学分析,特别是在考虑每个坐标集的特征值以及燃料小石中的裂变功率分布时。结果发现,在MM坐标生成方法中,轴向填充率是一致的,并且它与DEM生成的坐标之间的总体趋势相似。此外,发现模拟岩心的特征值与岩心中的卵石数量成正比。最后,在多组MM生成的坐标集内以及两种坐标生成方法的比较中,发现核的裂变功率分布在质量上是一致的。

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