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首页> 外文期刊>Annals of nuclear energy >Nuclear data uncertainty propagation analysis for depletion calculation in PWR and FR pin-cells
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Nuclear data uncertainty propagation analysis for depletion calculation in PWR and FR pin-cells

机译:核数据不确定性传播分析,用于PWR和FR针式电池的损耗计算

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In order to assess the nuclear data uncertainty propagation in the depletion calculation, a computational code named SUNDEW has been developed based on the home-developed lattice code NECP-CACTI. In the SUNDEW, Generalized Perturbation Theory (GPT) is applied to calculate sensitivity coefficients of response function with respect to the nuclear cross sections. Method of Characteristics (MOC) is employed to solve the transport equation, adjoint and generalized adjoint transport equations. Chebyshev Rational Approximation Method (CRAM) is implemented to solve the depletion equation and adjoint depletion equation. The sensitivity coefficients of K-eff and nuclide density with respect to the nuclear cross sections are verified by comparing with the results of direct perturbation calculation. The uncertainties on K-eff and the nuclide density at different depletions, which are induced by the nuclear cross sections uncertainties, are analyzed based on ENDF/B-VII.1 covariance data for LWR and fast reactor pin-cells. The numerical results show that there are significant differences between LWR and fast reactor pin-cells. The differences are mainly caused by the differences of the sensitivity coefficients between the LWR and fast reactor pin-cells. In addition, to identify the cross section improvement priority for nuclides, reactions and energy ranges, the dominant contributors to K-eff and nuclide density uncertainties are analyzed at different depletions. (C) 2016 Elsevier Ltd. All rights reserved.
机译:为了评估耗竭计算中核数据不确定性的传播,基于自行开发的格码NECP-CACTI,开发了一个名为SUNDEW的计算代码。在SUNDEW中,应用广义摄动理论(GPT)来计算相对于核截面的响应函数的灵敏度系数。采用特征方法(MOC)求解输运方程,伴随和广义伴随输运方程。 Chebyshev有理逼近方法(CRAM)用于解决耗竭方程和伴随耗竭方程。通过与直接摄动计算的结果进行比较,验证了K-eff和核素密度相对于核截面的敏感性系数。基于ENDF / B-VII.1轻水堆和快堆针状电池的协方差数据,分析了由核截面不确定性引起的K-eff和核素密度在不同耗竭状态下的不确定性。数值结果表明,轻水堆和快速反应堆针式电池之间存在显着差异。差异主要是由于轻水堆和快堆针式电池之间的灵敏度系数不同所致。此外,为了确定核素,反应和能量范围的横截面改进优先级,在不同的消耗量下分析了K-eff和核素密度不确定性的主要因素。 (C)2016 Elsevier Ltd.保留所有权利。

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