HTR-10一回路冷却剂中氚活度的测量

详细介绍了测量10 MW高温气冷试验堆一回路冷却剂中氚活度的方法。设计适用于HTR-10特点的氚收集装置,先后两次收集冷却剂中的氚,制成液样进而用液闪法进行测量,并根据试验结果推算HTR-10一回路冷却剂中氚的总活度。针对两次试验结果进行分析并与理论计算值相比较,验证了理论计算的正确性并由此进一步证明高温气冷堆的燃料包覆颗粒对放射性产物的阻挡作用完好,反应堆对环境的氚释放完全在设计要求范围内,符合相应的国家标准。

Tritium activity measurement of the primary loop coolant of HTR-10

This article introduces the tritium activity measurements of 10 MW high temperature gas-cooled reactor(HTR-10) in detail.The tritium collecting devices were well designed especially for HTR-10.The tritium in the sample gas from primary loop was collected for two times,and was made into liquid sample for liquid scintillation counting.Based on the measurement results,the total tritium activity in primary loop of HTR-10 is calculated.Comparing the measurement results with the theoretical calculation,it shows that the value of theoretical calculation is validated correct.The coated particles in the fuel element retain the radio-nuclides very well.While the tritium released to the environment conforms the design specifications and the national standards.