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首页> 外文期刊>Annals of nuclear energy >U_WB_1 - Fast nuclear fuel depletion code
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U_WB_1 - Fast nuclear fuel depletion code

机译：U_WB_1-快速核燃料消耗代码

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摘要

The research presented in this paper aims at the development and introduction of acomputational tool to evaluate advanced types of burnable absorbers (BA) in nuclear fuel. BAs compensate for the initial excess reactivity and consequently allow for lower power peaking factors and longer fuel cycles with higher fuel enrichments. Such a nuclear fuel design optimization requires a very fast depletion calculation in order to achieve useful results in a reasonable time. The state-of-the-art calculation scheme consists of consecutively solved inventory and transport equations for each depletion time step. Different calculation time reduction methods can be applied with the aim at simplifying or even omitting the transport part of the depletion scheme. The newly developed U_WB_1 code allows calculation time reduction by omitting the solution step for the Boltzmann transport equation. Therefore, microscopic cross sections are assumed to be constant throughout depletion calculation steps. The U_WB_1 consists of a point depletion code and a prepared set of nuclear data libraries for selected nuclear fuels. The U_WB_1 code is Fortran-based and employs features from state-of-art codes: (1) pointwise-based nuclear data library prepared with neutron spectra from the SCALE code package, (2) CRAM method for simplifying matrix exponential determination from SERPENT code and (3) LAPACK algebraic library for solving inverse matrices. Using typical desktop computers, solving one depletion time step for 3820 nudides takes approximately 10 s with the U_WB_1 code. A simplified depletion code will allow faster calculation analysis of BA parameters for optimized nuclear fuel design.
机译：本文提出的研究旨在开发和引入一种计算工具，以评估核燃料中高级可燃吸收剂（BA）的类型。 BA补偿了最初的过量反应性，因此允许较低的功率峰值因数和较长的燃料循环以及更高的燃料浓缩度。这样的核燃料设计优化需要非常快速的耗竭计算，以便在合理的时间内获得有用的结果。最新的计算方案由每个消耗时间步长连续求解的库存和运输方程式组成。可以应用不同的计算时间减少方法，以简化或什至省去耗竭方案的运输部分。新开发的U_WB_1代码通过省略玻尔兹曼输运方程的求解步骤，从而减少了计算时间。因此，在整个损耗计算步骤中，微观横截面被假定为恒定的。 U_WB_1包括一个点耗竭代码和一组针对所选核燃料的准备好的核数据库。 U_WB_1代码基于Fortran，并采用了最新代码的功能：（1）使用SCALE代码包中的中子谱准备的基于点的核数据库，（2）CRAM方法可简化从SERPENT代码确定矩阵指数的过程（3）LAPACK代数库，用于求解逆矩阵。使用典型的台式计算机，用U_WB_1代码解决3820个核素的耗尽时间步长大约需要10 s。简化的消耗代码将允许对BA参数进行更快的计算分析，以优化核燃料设计。

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  • 来源
    《Annals of nuclear energy》 |2014年第9期|333-339|共7页
  • 作者

    M. Lovecky; L. Piterka; J. Prehradny; R. Skoda;

  • 作者单位

    Regional Innovation Centre for Electrical Engineering, University of West Bohemia, Univerzitni 8, 306 14 Plzen, Czech Republic;

    Regional Innovation Centre for Electrical Engineering, University of West Bohemia, Univerzitni 8, 306 14 Plzen, Czech Republic;

    Regional Innovation Centre for Electrical Engineering, University of West Bohemia, Univerzitni 8, 306 14 Plzen, Czech Republic,Czech Technical University, Faculty of Mechanical Engineering, Technicka 4, Prague 6 CZ-160 07, Czech Republic;

    Regional Innovation Centre for Electrical Engineering, University of West Bohemia, Univerzitni 8, 306 14 Plzen, Czech Republic,Czech Technical University, Faculty of Mechanical Engineering, Technicka 4, Prague 6 CZ-160 07, Czech Republic,Texas A&M University, Department of Nuclear Engineering TAMU-3133, College Station, TX 77843, USA;

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  • 原文格式 PDF
  • 正文语种 eng
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  • 关键词

    Nuclear fuel; Depletion; Burnable absorber;

    机译：核燃料;消耗;可燃吸收体;

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