论文标题

核反应堆中子种群的渗滤特性

Percolation properties of the neutron population in nuclear reactors

论文作者

Dechenaux, Benjamin, Delcambre, Thomas, Dumonteil, Eric

论文摘要

反应堆物理学旨在研究反馈机制的影响,例如多普勒温度效应。然而,计算从这种耦合随机系统出现的宏观特性的数值方案需要定义中间量(例如温度场),这些量(例如温度场)弥合了随机中子场和确定性反馈之间的间隙。通过解释在反馈机制的影响下,将裂变培养基中的中子随机步行作为定向的渗透过程,并利用统计田地理论的出生死亡过程理论,我们将建立一个中子运输理论和反应堆物理学的随机模型。该模型的关键指数结合了涉及分数拉普拉斯的所得场方程的分析将表明,关键的扩散方程无法充分描述中子总体的空间分布,而是转移到关键的超扩散方程。对该方程式的分析将表明,反应堆核心可能会发展平均野外行为,从而质疑核工业当前使用的数值方案的可实现准确性。

Reactor physics aims at studying the neutron population in a reactor core under the influence of feedback mechanisms, such as the Doppler temperature effect. Numerical schemes to calculate macroscopic properties emerging from such coupled stochastic systems however require to define intermediate quantities (e.g. the temperature field), which are bridging the gap between the stochastic neutron field and the deterministic feedback. By interpreting the branching random walk of neutrons in fissile media under the influence of a feedback mechanism as a directed percolation process and by leveraging on the statistical field theory of birth death processes, we will build a stochastic model of neutron transport theory and of reactor physics. The critical exponents of this model, combined to the analysis of the resulting field equation involving a fractional Laplacian will show that the critical diffusion equation cannot adequately describe the spatial distribution of the neutron population and shifts instead to a critical super-diffusion equation. The analysis of this equation will reveal that non-negligible departure from mean field behavior might develop in reactor cores, questioning the attainable accuracy of the numerical schemes currently used by the nuclear industry.

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