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DETERMINATION OF CRITICAL EXPERIMENT CORRELATIONS FOR EXPERIMENTS INVOLVING ARRAYS OF LOW-ENRICHED FUEL RODS

机译:测定涉及低富富燃料杆阵列的实验的关键实验相关性

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Quantifying correlations among critical experiments has become a topic of interest over the last 10-15 years. Correlations arise from the shared use of fissile material, nonfissile materials, fixtures, and procedures in multiple experiments or multiple experiment series. A Monte Carlo sampling technique proposed as a viable technical method to evaluate these correlations has been implemented in the SCALE 6.2 Sampler sequence. This paper presents an investigation of the use of this new tool and technique for low-enriched uranium pin array experiments with a thermal neutron energy spectrum. The Nuclear Energy Agency's Expert Group on Uncertainty Analyses for Criticality Safety Assessments has been examining methods of calculating the correlation coefficients among experiments from the LCT-007 and LCT-039 series. Results for two scenarios are presented to demonstrate the impact of pin pitch uncertainty modeling on the correlation coefficients. The convergence of the correlation coefficients is also investigated. Additional studies examine the impact of the stochastic uncertainty and the use of continuous-energy Monte Carlo for individual realizations on the correlation coefficients. Correlation coefficients are also determined for the LCT-042 experiment series. This experiment series differs from other experiments because unique poison panels and fuel array separation distances may reduce correlation of the individual experiments within the series. The effects of pin pitch uncertainty and stochastic uncertainty are also examined for this series. Comparing the results of the two sets of experiments shows potential conclusions that can be drawn regarding viability of the Monte Carlo sampling technique for determining critical experiment correlations.
机译:关键的实验中量化的相关性已成为在过去10 - 15年的感兴趣的话题。的相关性从所述共享使用裂变材料,不裂变的材料,固定装置,并在多个实验或多个实验系列程序的出现。提出一个可行的技术方法来评估这些相关的蒙特卡洛采样技术已经在规模6.2采样序列得到落实。本文介绍了使用这一新工具和技术与热中子能谱低浓缩铀针阵列实验的调查。核能机构的专家组对临界安全评估分析的不确定性一直在研究从LCT-007和LCT-039系列的实验中计算的相关系数的方法。结果两种情况都证明引脚间距不确定性模型对相关系数的影响。相关系数的融合进行了研究。进一步的研究探讨随机不确定性的影响,对相关系数的实现个人使用连续能量蒙特卡洛的。相关系数也确定了LCT-042系列实验。这从其他实验的实验系列不同,因为独特毒物板和燃料阵列的分隔距离可减小串联内的各个实验的相关性。还审查了该系列的引脚间距不确定性和随机不确定性的影响。两组实验的结果比较示出了可绘制的蒙特卡罗抽样技术的关于生存力测定临界实验相关的潜在的结论。

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