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Sensitivity and uncertainty analysis of nuclear reactor reactivity coefficients by Monte Carlo second-order perturbation method

机译:蒙特卡罗二阶摄动法对核反应堆反应系数的敏感性和不确定性分析

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The uncertainty quantification of the reactivity coefficients such as the fuel temperature coefficient (FTC) and the moderator density coefficient (MDC) is crucial for the nuclear reactor safety margin evaluation. This paper proposes a continuous-energy MC second-order perturbation (MC2P) method as a new way to estimate efficiently the sensitivity of reactivity coefficients to nuclear cross section data. The proposed MC2P method takes into account the second-order effects of the fission operator and the fission source distribution. The effectiveness of the MC2P method implemented in a Seoul National University MC code, McCARD, is demonstrated in a Godiva U-235 density coefficient problem via comparison of its results with direct subtraction MC calculation. It is shown that the new method can predict the cross section sensitivities of the reactivity coefficient more accurately even with much smaller number of MC history simulations than the direct subtraction MC method. It is also shown that the proposed method is applicable for quantifying the uncertainties of the MDC of a LWR pin cell problem and the FTC of a CANDU 6 lattice cell problem due to the uncertainties of the nuclear cross section input data represented by nuclear cross section covariance data. (C) 2018 Elsevier Ltd. All rights reserved.
机译:反应性系数(例如燃料温度系数(FTC)和减速剂密度系数(MDC))的不确定性量化对于核反应堆安全裕度评估至关重要。本文提出了一种连续能量MC二次扰动(MC2P)方法,作为一种有效估算反应性系数对核截面数据敏感性的新方法。所提出的MC2P方法考虑了裂变算符和裂变源分布的二阶效应。通过将其结果与直接减法MC计算进行比较,在首尔国立大学MC代码McCARD中实施的MC2P方法的有效性在Godiva U-235密度系数问题中得到了证明。结果表明,与直接减法MC方法相比,即使使用更少的MC历史模拟次数,该新方法也可以更准确地预测反应系数的截面灵敏度。还表明,由于以核横截面协方差表示的核横截面输入数据的不确定性,所提出的方法适用于量化LWR pin单元问题的MDC和CANDU 6晶格问题的FTC的不确定性数据。 (C)2018 Elsevier Ltd.保留所有权利。

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