HTR-10一回路放射性石墨粉尘实验系统设计及研究

在10MW高温气冷堆(HTR-10)氦净化系统中,设计并建造了用于取样收集一回路放射性石墨粉尘的实验系统。结合国外已有的研究结果,根据HTR-10氦净化系统的运行参数进行了模拟计算。计算结果表明,该实验系统能有效过滤收集到的放射性石墨粉尘。所设计的取样过滤器便于拆卸和后期测量,可实现对放射性石墨粉尘进行长期系统的研究,给出反应堆不同运行工况下一回路氦净化系统中石墨粉尘及固体裂变核素活度的信息,将为HTR-10高温气冷堆裂变产物行为研究提供大量重要的实验研究数据。

Design and Study of Radioactive Graphite Dust Experimental System in Primary Loop of HTR-10

In the helium purification system of 10 MW high temperature gas-cooled reactor (HTR-10), an experimental system which could be used to sample the radioactive graphite dust in the primary loop was designed and built. Combined with international research results, a simulation was done according to parameters of the helium purification system of HTR-10. The results indicate that the experimental system can sample the radioactive graphite dust effectively. The sampling filter can be disassembled easily for further measurement, and used to do a long term systematical study on the radioactive graphite dust. It can provide the informations of the graphite dust and the activity of solid fission nuclides in the primary loop in different operation situations, and supply large amount of important experimental data to study the behavior of fission products in HTR-10.