本工作是在БФС-101-1(钚堆芯)临界装置上采用带富集铀(235U的富集度为90%)和钚(239Pu富集度为99.5%)涂层的小型裂变室方法测量平均裂变截面比?σf9/?σf5。进行轴向平均裂变截面比?σf9/?σf5测量时,在堆芯中心(其位置坐标为(0,0,0))燃料组件位置处把组件替换为实验导管。小 In this work, a small fission chamber method with enrichment of uranium (90% enrichment of 235U) and plutonium (99.5% enrichment of 239Pu) coatings was applied to the БФС-101-1 (plutonium core) critical facility Measure the average fission cross section ratio σf9 / σf5. For an axial average fission section ratio σf9 / σff5, the assembly is replaced with an experimental catheter at the core of the assembly (at position coordinates (0,0,0)) at the location of the fuel assembly. small