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首页> 外文期刊>Progress in Nuclear Energy >3D neutron diffusion computational code based on GFEM with unstructured tetrahedron elements: A comparative study for linear and quadratic approximations
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3D neutron diffusion computational code based on GFEM with unstructured tetrahedron elements: A comparative study for linear and quadratic approximations

机译:基于具有非结构化四面体元素的GFEM的3D中子扩散计算代码:线性近似和二次近似的比较研究

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In the present study, the comparison between the results obtained from the linear and quadratic approximations of the Galerkin Finite Element Method (GFEM) for neutronic reactor core calculation was reported. The sensitivity analysis of the calculated neutron multiplication factor, neutron flux and power distributions in the reactor core vs. the number of the unstructured tetrahedron elements and order of the considered shape function was performed. The cost of the performed calculation using linear and quadratic approximation was compared through the calculation of the FOM. The neutronic core calculation was performed for both rectangular and hexagonal geometries. Both the criticality and fixed source calculations were done using the developed GFEM-3D computational code. An acceptable accuracy with low computational cost is the main advantage of applying the unstructured tetrahedron elements. The generated unstructured tetrahedron elements with Gambit software were used in the GFEM-3D computational code via a developed interface. The criticality calculation was benchmarked against the valid data for IAEA-3D and VVER-1000 benchmark problems. Also, the neutron fixed source calculation was validated through the comparison with the similar computational code. The results show that the accuracy of the calculation for the both linear and quadratic approximations improves vs. the number of elements. Quadratic approximation gives acceptable results for almost all considered number of the elements, while the results obtained from the linear approximation have good accuracy for only high number of the elements. (C) 2016 Elsevier Ltd. All rights reserved.
机译:在本研究中,报告了用于中子反应堆堆芯计算的Galerkin有限元方法(GFEM)的线性近似和二次近似所得结果之间的比较。进行了计算得出的中子倍增因子,反应堆堆芯中子通量和功率分布对非结构化四面体元素数量以及所考虑形状函数阶数的敏感性分析。通过FOM的计算比较了使用线性和二次近似进行的计算成本。对矩形和六边形都进行了中子堆芯计算。关键性和固定源计算均使用开发的GFEM-3D计算代码完成。可接受的精度和较低的计算成本是应用非结构化四面体元素的主要优点。通过开发的界面,使用Gambit软件生成的非结构化四面体元素被用于GFEM-3D计算代码中。关键度计算是针对IAEA-3D和VVER-1000基准测试问题的有效数据进行基准测试的。此外,通过与类似计算代码的比较,验证了中子固定源的计算。结果表明,线性近似和二次近似的计算精度均相对于元素数量有所提高。对于几乎所有考虑数量的元素,二次逼近都能给出可接受的结果,而从线性逼近中获得的结果仅对大量元素具有良好的精度。 (C)2016 Elsevier Ltd.保留所有权利。

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