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为分析核数据引起的中国实验快堆(CEFR)keff计算值的不确定度,推导出基于一阶微扰方法的keff灵敏度计算式,基于多群节块扩散理论对keff的灵敏度计算式进行离散求解,并在快堆中子学分析系统(NAS)的基础上开发不确定度分析程序SUAPH,并对程序进行验证。根据现有协方差数据,采用SUAPH完成CEFR首炉堆芯keff的灵敏度和不确定度分析,由核数据引起的CEFR首炉堆芯keff的不确定度约为2.02%。
In order to analyze the uncertainty of keff value of CEFR caused by nuclear data, the keff sensitivity calculation formula based on the first-order perturbation method is deduced, and the keff sensitivity calculation formula is discretized based on the multi-group nodal diffusion theory Based on the Fast Reactor Neutronics Analysis System (NAS), the program SUAPH is developed and verified. Based on the available covariance data, SUAPH was used to complete the sensitivity and uncertainty analysis of the CEFR first reactor core keff. The uncertainty of the CEFR first reactor core keff caused by nuclear data was about 2.02%.