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Sensitivity and uncertainty analysis for eigenvalue and few-group constants of reactor-physics calculations

机译:对抗物理计算特征值和少数群常数的敏感性和不确定性分析

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The effects of nuclear-data uncertainties on the predictions of the reactor-physics calculations are quantified in this paper. Uncertainty analysis has been applied to the TMI-1 assembly at both Hot Zero Power (HZP) and Hot Full Power (HFP) conditions, propagating the nuclear-data uncertainties to the eigenvalue and few-group constants. The statistical sampling method has been applied to the uncertainty analysis for lattice calculations of TMI-1 assembly. The 172-group WIMSD-4 formatted microscopic cross-section library and corresponding cross-section covariance matrices based on the ENDF/B-VII.l have been generated and applied for the uncertainty analysis. From the numerical results of the uncertainty analysis, it can be observed that the relative uncertainties of the eigenvalue and two-group constants at HFP are a little larger than these at HZP. The v, and v_p covariance matrices of ~(235)U impact the uncertainty results notably. Both at HZP and HFP, the relative uncertainty of the eigenvalue is about (4.7±0.09)%o (applying v_p covariance of ~(235)U) or (7.1±0.20) %o (applying v, covariance of ~(235)U); the relative uncertainties of two-group constants vary from about (2.9±0.06)%o (for ∑_(t,2)) to (11,9 ± 0.34)%o (for ∑_(s,1,2)).
机译:本文量化了核数据不确定性对反应器 - 物理计算预测的影响。不确定性分析已在热零功率(HZP)和热的全功率(HFP)条件下应用于TMI-1组件,将核数据不确定性传播到特征值和少量常量。统计采样方法已应用于TMI-1组装晶格计算的不确定性分析。已经产生了基于ENDF / B-VII.L的172组WIMSD-4格式的微观横截面库和相应的横截面协方差矩阵,并施加了不确定性分析。从不确定性分析的数值结果来看,可以观察到,HFP的特征值和两组常数的相对不确定性比在HZP处大。 〜(235)U的V和V_P协方差矩阵尤其影响不确定性结果。在HzP和HFP下,特征值的相对不确定度约为(4.7±0.09)%O(施用〜(235)u)或(7.1±0.20)%O(应用V,〜(235)的协方差u);两组常数的相对不确定性从约(2.9±0.06)%O(σ_(t,2))变化(11,9±0.34)%O(对于σ_(s,1,2)) 。

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