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Sensitivity Analysis and Uncertainty Quantification of FFTF Cycle 8C Using the NEAMS Workbench

机译:使用NEAMS工作台进行FFTF循环8C的灵敏度分析和不确定度量化

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The FFTF Cycle 8C core was modeled using the NEAMS Workbench PyARC interface to compute the reactivity coefficients, the neutron and the gamma power distributions. These will be used for benchmark simulations using SAS4A/SASSYS-1. The present work discusses the impact of cross-section processing approximation and of nuclear data uncertainty on the eigenvalue and reactivity feedback coefficients. For FFTF, both the heterogeneous cross-section treatment and the TWODANT step were found to provide relatively marginal impact on the reactivity coefficients, but do impact the k-effective by 650pcm. In addition, the nuclear data uncertainty was propagated to the neutronic feedback coefficients and was found to be responsible for 1% to 18% uncertainty on some reactivity feedback coefficients. These uncertainties will be propagated through the LOFWOS transient in FFTF to see if the uncertainties coming from the nuclear data help explain some of the discrepancy observed between the best estimate results and the experiment.
机译:使用NEAMS Workbench PyARC接口对FFTF Cycle 8C核进行建模,以计算反应系数,中子和伽马功率分布。这些将用于使用SAS4A / SASSYS-1的基准仿真。本工作讨论了截面处理近似和核数据不确定性对特征值和反应性反馈系数的影响。对于FFTF,发现异质截面处理和TWODANT步骤都对反应系数产生了相对较小的影响,但确实对650pcm的k值产生了影响。另外,核数据的不确定性会传播到中子反馈系数中,并被发现在某些反应性反馈系数中占1%至18%的不确定性。这些不确定性将通过FFTF中的LOFWOS瞬态传播,以查看来自核数据的不确定性是否有助于解释最佳估计结果与实验之间观察到的某些差异。

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  • 来源
    《Transactions of the American nuclear society 》 |2019年第11期| 1373-1376| 共4页
  • 作者单位

    Nuclear Science and Engineering Division Argonne National Laboratory 9700 Cass Ave Lemont IL 60439 USA University of the Witwatersrand Private bag X3 Wits 2050 Johannesburg South Africa;

    Nuclear Science and Engineering Division Argonne National Laboratory 9700 Cass Ave Lemont IL 60439 USA;

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