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Kinetic parameters evaluation of PWRs using static cell and core calculation codes

机译:使用静态单元格和堆芯计算代码评估压水堆的动力学参数

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In this paper, evaluation of the kinetic parameters (effective delayed neutron fraction and prompt neutron lifetime) in PWRs, using static cell and core calculation codes, is reported. A new software has been developed to link the WIMS, BORCES and CITATION codes in Visual C# computer programming language. Using the WIMS cell calculation code, multigroup microscopic cross-sections and number densities of different materials can be generated in a binary file. By the use of BORGES code, these binary-form cross-sections and number densities are converted to a format readable by the CITATION core calculation code, by which the kinetic parameters can be finally obtained. This software is used for calculation of the kinetic parameters in a typical WER-1000 and NOK Beznau reactor. The ratios β_(eff)/(β_(eff))cofe , which are the important input data for the reactivity accident analysis, are also calculated. Benchmarking of the results against the final safety analysis report (FSAR) of the aforementioned reactors shows very good agreements with these published documents.
机译:在本文中,报告了使用静态电池和堆芯计算代码对压水堆中的动力学参数(有效的延迟中子分数和迅速的中子寿命)进行评估。已开发出一种新软件,以Visual C#计算机编程语言链接WIMS,BORCES和CITATION代码。使用WIMS单元计算代码,可以在二进制文件中生成不同材料的多组微观截面和数量密度。通过使用BORGES代码,这些二进制形式的横截面和数量密度被转换为CITATION核心计算代码可读取的格式,由此最终可以获得动力学参数。该软件用于计算典型WER-1000和NOK Beznau反应堆的动力学参数。还计算了比率β_(eff)/(β_(eff))cofe,它们是反应性事故分析的重要输入数据。将结果与上述反应堆的最终安全分析报告(FSAR)进行基准比较,表明与这些已发布的文件非常吻合。

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