压缩针接针截面的多元表示

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY EPJ Nuclear Sciences & Technologies Pub Date : 2021-01-01 DOI:10.1051/EPJN/2021006
D. Tomatis
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引用次数: 3

摘要

自20世纪80年代以来,工业堆芯计算采用两步方案,该方案基于较少能量群和均匀参考几何形状的先前截面准备。燃料组件区域的空间均匀化是目前最常用的计算选项,它依赖于使用粗网格的高效节点求解器。然后通过脱均质技术重建针方向的反应速率。然而,核心计算的未来趋势是向针接针的显式表示方向发展,在许多物理条件下,在单个针中均匀化少数基团截面,并选择许多核素用于简化耗尽链。所得到的数据模型需要占用磁盘文件的相当大的内存,并且评估所有数据所需的时间超过了多物理场反应堆计算的实际可行性的限制。在这项工作中,我们研究了典型的压水堆燃料组件的Hotelling变换对pin-by-pin均质截面的压缩。这些量在装配的不同物理状态下的重建,然后通过仅插值几个压缩系数来解决,而不是单独插值每个均匀截面。可以观察到内存节省超过90%,这在插入少量组数据时在运行时带来了重要的收益。
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A multivariate representation of compressed pin-by-pin cross sections
Since the 80’s, industrial core calculations employ the two-step scheme based on prior cross sections preparation with few energy groups and in homogenized reference geometries. Spatial homogenization in the fuel assembly quarters is the most frequent calculation option nowadays, relying on efficient nodal solvers using a coarse mesh. Pin-wise reaction rates are then reconstructed by dehomogenization techniques. The future trend of core calculations is moving however toward pin-by-pin explicit representations, where few-group cross sections are homogenized in the single pins at many physical conditions and many nuclides are selected for the simplified depletion chains. The resulting data model requires a considerable memory occupation on disk-files and the time needed to evaluate all data exceeds the limits for practical feasibility of multi-physics reactor calculations. In this work, we study the compression of pin-by-pin homogenized cross sections by the Hotelling transform in typical PWR fuel assemblies. The reconstruction of these quantities at different physical states of the assembly is then addressed by interpolation of only a few compressed coefficients, instead of interpolating separately each homogenized cross section. Savings in memory higher than 90% are observed, which result in important gains in runtime when interpolating the few-group data.
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来源期刊
EPJ Nuclear Sciences & Technologies
EPJ Nuclear Sciences & Technologies NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
1.00
自引率
20.00%
发文量
18
审稿时长
10 weeks
期刊最新文献
Technical note: stable and unstable reactors Templates of expected measurement uncertainties for neutron-induced capture and charged-particle production cross section observables Templates of expected measurement uncertainties for (n, xn) cross sections Templates of expected measurement uncertainties for total neutron cross-section observables Templates of expected measurement uncertainties for prompt fission neutron spectra
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