Evaluation and Propagation of the 239Pu Fission Cross-Section Uncertainties Using a Monte Carlo Technique
Evaluation and Propagation of the 239Pu Fission Cross-Section Uncertainties Using a Monte Carlo Technique
复制标题
使用蒙特卡罗技术评估和传播 239Pu 裂变截面不确定性
DOI：
10.13182/nse06-a2589
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发表时间：
2006
影响因子：
1.2
通讯作者：
R. Little
中科院分区：
文献类型：
--
作者：
T. Kawano;K. Hanson;S. Frankle;P. Talou;M. Chadwick;R. Little
摘要我们提出了一种核应用中不确定度量化的方法，该方法结合了微分截面数据的协方差评估和使用中子输运计算匹配临界实验的误差传播。用PARTISN程序进行一维中子输运计算，研究了~(239)Pu裂变截面不确定度的降低。使用贝叶斯方法将239Pu不同截面数据的评估与临界性测量(Jezebel)相结合。为了量化这种计算中的不确定性，我们生成一组代表协方差矩阵的随机横截面样本，并估计计算量的分布，如临界性。我们表明，Jezebel数据的加入减少了估计中子多重数的不确定性。
Abstract We present an approach to uncertainty quantification for nuclear applications that combines the covariance evaluation of differential cross-section data and the error propagation from matching a criticality experiment using a neutron-transport calculation. We have studied the reduction in uncertainty of 239Pu fission cross sections by using a one-dimensional neutron-transport calculation with the PARTISN code. The evaluation of 239Pu differential cross-section data is combined with a criticality measurement (Jezebel) using a Bayesian method. To quantify the uncertainty in such calculations, we generate a set of random samples of the cross sections, which represents the covariance matrix, and estimate the distribution of calculated quantities, such as criticality. We show that inclusion of the Jezebel data reduces uncertainties in estimating neutron multiplicity.