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Calculation of core safety parameters and uncertainty analyses during unprotected transients for the ALLEGRO and a sodium-cooled fast reactor

机译:ALLEGRO和钠冷快堆无保护瞬变期间的核心安全参数计算和不确定性分析

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摘要

The calculation of the essential core safety parameters in fast spectrum reactors are loaded with large uncertainties due to the particularly large uncertainty of nuclear data, modelling uncertainties and possible mistakes by users. These core safety parameters such as coefficients of reactivity, power peaking factors and point-kinetics parameters play an important role during unprotected transients. The contributions to the uncertainties of the target parameters (e.g. peak cladding temperature) from the core safety parameters can be determined by uncertainty and sensitivity analyses.
机译:由于核数据特别不确定,建模不确定以及用户可能的错误,快速频谱反应堆中基本堆芯安全参数的计算存在很大的不确定性。这些核心安全参数,例如反应系数,功率峰值因子和点动力学参数,在无保护的瞬变过程中起着重要的作用。可以通过不确定性和灵敏度分析来确定核心安全参数对目标参数不确定性(例如峰值包层温度)的不确定性的贡献。

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