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NUCLEAR DATA UNCERTAINTY PROPAGATION ANALYSIS FOR LWR DEPLETION CALCULATION

机译:轻水堆损耗计算的核数据不确定性传播分析

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In order to assess the uncertainties induced by nuclear cross sections in the depletion calculation, a computational code named SUNDEW has been developed based on the home-developed lattice code CACTI. In the SUNDEW, Generalized Perturbation Theory (GPT) is applied to calculate sensitivity coefficient of response functions with respect to the nuclear cross sections. Method of Characteristic (MOC) is employed to solve the transport equation, adjoint and generalized adjoint transport equation. 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 calculation results of direct perturbation calculation (DP). The uncertainties of K_(eff) and number density are analyzed for the PWR burn-up pin-cell benchmark proposed by the NEA/OECD. The numerical results with ENDF/B-Ⅶ.1 covariance data are compared with those from JENDL4.0 covariance data, which reveal that the uncertainties assessment and the source of covariance data have a strong relationship. In addition, to identify the cross section improvement priority for nuclide, reaction and energy range, the dominant contributors of the K_(eff) and number density uncertainties are analyzed in different depletions.
机译:为了评估在耗尽计算中由核横截面引起的不确定性,基于自行开发的晶格代码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(DP)的计算结果进行比较,验证了K_(eff)和核素密度对核截面的敏感性系数。针对NEA / OECD提出的PWR烧毁引脚电池基准,分析了K_(eff)和数量密度的不确定性。将ENDF /B-Ⅶ.1协方差数据的数值结果与JENDL4.0协方差数据的数值结果进行比较,这表明不确定性评估与协方差数据的来源有很强的关系。另外,为了确定核素,反应和能量范围的横截面改进优先级,在不同的消耗下分析了K_(eff)和数密度不确定性的主要贡献因素。

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