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.