环形燃料反应堆通量密度分布测量

相对中子通量密度分布是反应堆的重要物理参数之一，测量环形燃料零功率反应堆堆芯相对中子通量密度分布对了解环形燃料堆芯反应堆物理特性及开展安全分析具有指导意义。本文在环形燃料堆芯多边形装载下，采用箔活化法对辐照后燃料元件外表面不同位置金箔的γ活度进行测量，得到不同位置燃料元件轴向、径向的相对中子通量密度分布，并将测量值与蒙特卡罗理论计算值进行比对。结果表明：实验测量值与理论计算值最大相对偏差在12%以内，相对中子通量密度分布测量结果符合实验设计预期，现有蒙特卡罗分析手段可较好地分析堆内元件轴向通量密度分布情况。本文结果可为环形燃料的工程化应用提供重要的数据支撑。

Flux Density Distribution Measurement in Annular Fuel Reactor

The relative neutron flux density distribution is one of the essential physical parameters of the reactor. Measuring the relative neutron flux density distribution of the annular fuel zero-power reactor core has guiding significance for understanding the physical characteristics of the annular fuel core reactor and conducting safety analysis. In this paper, the γ activity of the gold foil at different positions on the outer surface of the fuel cell after irradiation was measured by foil activation method under polygonal loading of annular fuel core. The axial and radial relative neutron flux density distributions of fuel cell at different positions were obtained, and the measured values were compared with the values calculated by Monte Carlo theory. The results show that the maximum relative deviation between experimental measurement and theoretical calculation is within 12%. The measurement results of relative neutron flux density distribution are in line with the measure design expectations. The existing Monte Carlo analysis methods can better analyze the axial flux density distribution of the components in the reactor. This study provides essential data support for the engineering application of annular fuel.