A dataset of "Assembly-level analysis on temperature coefficient of reactivity in a graphite-moderated fuel salt reactor fueled with low-enriched uranium"

The data file for the article "Assembly-level analysis on temperature coefficient of reactivity in a graphite-moderated fuel salt reactor fired with low-enriched uranium" is available here. The temperature coefficient of reactivity calculations made using Monte Carlo code are included in this dataset. A graphite-moderated fuel salt assembly that was used in the calculation is schematically shown in Fig1. The variations in various reactivity coefficients brought on by the Doppler effect, fuel salt density effect, fuel salt temperature effect, graphite moderator temperature effect, and total temperature effect are represented by the prefix Fig2–Fig7. The image used in the main manuscript is in the eps file, and the calculation data are in the opju file.

《低富集铀燃料石墨慢化熔盐堆反应性温度系数的组件级分析》一文的数据集文件可在此处获取。本数据集包含使用蒙特卡洛（Monte Carlo）程序计算得到的反应性温度系数相关结果。本次计算所采用的石墨慢化熔盐堆组件的示意图如图1所示。以图2至图7为前缀的图像，分别对应多普勒效应、熔盐密度效应、熔盐温度效应、石墨慢化剂温度效应以及总温度效应所引发的各类反应性系数的变化情况。主稿件中使用的图像存储于eps格式文件内，计算数据则收录于opju格式文件中。