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首页> 外文期刊>Progress in Nuclear Energy >Design and implementation of a relational database of macroscopic cross-sections for steady-state and transient analysis in a medium sized PWR
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Design and implementation of a relational database of macroscopic cross-sections for steady-state and transient analysis in a medium sized PWR

机译:中等截面压水堆中用于稳态和瞬态分析的宏观截面关系数据库的设计和实现

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This paper deals with the design and implementation of a relational database of macroscopic cross-sections as well as validation and its usage as a component in steady-state and transient analysis. These types of analysis are definitely designated as data-driven processes in which their behavior is changed based on data. The data in this manner can be the variation of fuel composition density as well as the fuel temperature during the reactor operation or in some accidents. In order to gain the accurate results in transient analysis, applying these variations is inevitable. Therefore, for each changing in fuel behavior, the new set of macroscopic cross-sections must be reproduced by performing the lattice calculations at run-time. During recent years some approaches have been done in both academic and commercial areas to take advantage of already calculated cross-sections instead of recalculate them by lattice codes during the analysis. Using this approach leverages the computation performance by reducing the floating point operations which can decrease the CPU load as well as the calculation time. Although this approach delivers a good performance in terms of time and computation, when a large number of fuel or reactor core circumstances are subjected to be analyzed the accuracy is became an important point. In this situation the cross-sections for all expected conditions must be already calculated. This cause the large number of cross-section data which must be stored and managed somehow. The system applied in this study to store and manage these cross-section data sets is a relational database management system (RDBMS) which is based on Microsoft SQL Server 2008 Management System. The node wise macroscopic cross-sections for each nominal and off-nominal of a typical medium sized PWR reactor core conditions which are calculated by WIMS-D5 and CITATION codes are tabulated in this system and can be retrieved by structured query language extremely rapid on demand.
机译:本文涉及宏观横截面的关系数据库的设计和实现,以及其在稳态和瞬态分析中的验证和使用。明确将这些类型的分析指定为数据驱动的过程,其中,它们的行为将根据数据进行更改。以这种方式的数据可以是反应堆运行期间或某些事故中燃料成分密度以及燃料温度的变化。为了在瞬态分析中获得准确的结果,应用这些变化是不可避免的。因此,对于燃料行为的每次变化,必须通过在运行时执行晶格计算来再现新的宏观横截面集。近年来,在学术和商业领域都采取了一些方法来利用已经计算出的横截面,而不是在分析过程中通过晶格代码重新计算它们。使用此方法可通过减少浮点运算来利用计算性能,从而减少CPU负载和计算时间。尽管这种方法在时间和计算方面都具有良好的性能,但是当要分析大量燃料或反应堆堆芯情况时,精度成为重要的一点。在这种情况下,必须已经计算出所有预期条件的横截面。这导致必须以某种方式存储和管理大量横截面数据。本研究中用于存储和管理这些横截面数据集的系统是一个基于Microsoft SQL Server 2008管理系统的关系数据库管理系统(RDBMS)。通过WIMS-D5和CITATION代码计算的典型中型压水堆堆芯条件的每个标称和标称值的节点级宏观截面都在该系统中制成表格,并且可以按需快速地通过结构化查询语言检索。

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