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MOCABA: A general Monte Carlo-Bayes procedure for improved predictions of integral functions of nuclear data

机译:MOCABA:改进蒙特卡罗-贝叶斯程序的核数据积分函数的预测

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摘要

MOCABA is a combination of Monte Carlo sampling and Bayesian updating algorithms for the prediction of integral functions of nuclear data, such as reactor power distributions or neutron multiplication factors. Similarly to the established Generalized Linear Least Squares (GLLS) methodology, MOCABA offers the capability to utilize integral experimental data to reduce the prior uncertainty of integral observables. The MOCABA approach, however, does not involve any series expansions and, therefore, does not suffer from the breakdown of first-order perturbation theory for large nuclear data uncertainties. This is related to the fact that, in contrast to the GLLS method, the updating mechanism within MOCABA is applied directly to the integral observables without having to "adjust" any nuclear data. A central part of MOCAB-A is the nuclear data Monte Carlo program NUDUNA, which performs random sampling of nuclear data evaluations according to their covariance information and converts them into libraries for transport code systems like MCNP or SCALE. What is special about MOCABA is that it can be applied to any integral function of nuclear data, and any integral measurement can be taken into account to improve the prediction of an integral observable of interest. In this paper we present two example applications of the MOCABA framework: the prediction of the neutron multiplication factor of a water-moderated PWR fuel assembly based on 21 criticality safety benchmark experiments and the prediction of the power distribution within a toy model reactor containing 100 fuel assemblies.
机译:MOCABA是蒙特卡洛采样和贝叶斯更新算法的组合,用于预测核数据的整体功能,例如反应堆功率分布或中子倍增因子。与已建立的广义线性最小二乘(GLLS)方法类似,MOCABA提供了利用积分实验数据来减少积分可观测量的先验不确定性的能力。但是,MOCABA方法不涉及任何级数展开,因此,不会因大型核数据不确定性而遭受一阶扰动理论的破坏。这与以下事实有关:与GLLS方法相反,MOCABA中的更新机制直接应用于积分可观测量,而无需“调整”任何核数据。 MOCAB-A的核心部分是核数据蒙特卡洛程序NUDUNA,该程序根据其协方差信息对核数据评估进行随机采样,并将其转换为运输代码系统(如MCNP或SCALE)的库。 MOCABA的特殊之处在于它可以应用于核数据的任何积分函数,并且可以考虑使用任何积分测量来改进对感兴趣的可观测积分的预测。在本文中,我们介绍了MOCABA框架的两个示例应用:基于21个临界安全基准实验对水控压水堆燃料组件的中子倍增因子的预测以及对包含100种燃料的玩具模型反应堆内功率分布的预测组件。

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  • 来源
    《Annals of nuclear energy》 |2015年第3期|514-521|共8页
  • 作者单位

    AREVA GmbH - Dep. Radiology & Criticality, Kaiserleistrasse 29, 63067 Offenbach am Main, Germany;

    AREVA GmbH - Dep. Radiology & Criticality, Kaiserleistrasse 29, 63067 Offenbach am Main, Germany;

    AREVA GmbH - Dep. Radiology & Criticality, Kaiserleistrasse 29, 63067 Offenbach am Main, Germany;

    AREVA GmbH - Dep. Radiology & Criticality, Kaiserleistrasse 29, 63067 Offenbach am Main, Germany;

    AREVA GmbH - Dep. Neutronics, Paul-Gossen-Strasse 100, 91052 Erlangen, Germany;

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  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Uncertainty analysis; Nuclear data; Monte Carlo methods; Nuclear criticality safety; Reactor analysis;

    机译:不确定性分析;核数据;蒙特卡洛方法;核临界安全性;反应堆分析;

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