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Uncertainty and correlation analysis of lead nuclear data on reactor parameters for the European Lead Cooled Training Reactor

机译:欧洲铅冷训练反应堆的铅核反应堆参数数据的不确定性和相关性分析

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摘要

The Total Monte Carlo (TMC) method was used in this study to assess the impact of Pb-204, 206, 207, 208 nuclear data uncertainties on reactor safety parameters for the ELECTRA reactor. Relatively large uncertainties were observed in the k-eff and the coolant void worth (CVW) for all isotopes except for Pb-204 with signicant contribution coming from Pb-208 nuclear data; the dominant eectcame from uncertainties in the resonance parameters; however, elastic scattering cross section and the angular distributions also had signicant impact. It was also observed that the k-eff distribution for Pb-206, 207, 208 deviates from a Gaussian distribution with tails in the high k-eff region. An uncertainty of 0.9% on the k-eff and 3.3% for the CVW due to lead nuclear data were obtained. As part of the work, cross section-reactor parameter correlations were also studied using a Monte Carlo sensitivity method. Strong correlations were observed between the k-eff and (n,el) cross section for all the lead isotopes. The correlation between the (n,inl) and the k-eff was also found to be signicant.
机译:本研究使用总蒙特卡洛(TMC)方法评估Pb-204、206、207、208核数据不确定性对ELECTRA反应堆安全性参数的影响。除Pb-204以外,所有同位素的k-eff和冷却剂空隙值(CVW)都存在较大的不确定性,而Pb-208核数据的贡献很大。共振参数的不确定性决定了主要作用;但是,弹性散射截面和角度分布也有显着影响。还观察到,Pb-206、207、208的k-eff分布与高k-eff区域中带有尾部的高斯分布偏离。由于铅核数据的存在,k-eff的不确定度为0.9%,CVW的不确定度为3.3%。作为工作的一部分,还使用蒙特卡罗灵敏度方法研究了截面反应器参数的相关性。对于所有铅同位素,在k-eff截面和(n,el)截面之间观察到强相关性。 (n,inl)和k-eff之间的相关性也被发现是重要的。

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