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Monitoring and Recovery of Tritium in a Fusion Test Facility
Fusion Science and Technology ( IF 0.9 ) Pub Date : 2020-05-05 , DOI: 10.1080/15361055.2020.1718840
Masahiro Tanaka 1, 2 , Naoyuki Suzuki 1 , Hiromi Kato 1 , Chie Iwata 1 , Naofumi Akata 1 , Hiroshi Hayashi 1 , Hitoshi Miyake 1
Affiliation  

Abstract In a large fusion test facility, when a deuterium-plasma experiment is conducted a small amount of tritium is produced by the d(d, p)t reaction. From the viewpoints of radiation management and public acceptance, the tritium monitoring and recovery systems were developed and installed for the fusion test device. As for the tritium monitoring equipment, an expiratory test system of tritium was utilized for the internal dose assessment of workers. Active tritium samplers were operated continuously to monitor the amount of tritium released from the stack. As for the tritium recovery equipment, an exhaust detritiation system (EDS) for the plasma experiment has been developed and installed at the downstream of the vacuum pumping system in the fusion test device. All of the exhausted tritium from the vacuum vessel was treated by the EDS during the deuterium-plasma experimental campaign. Then, the tritium recovery rate achieved was more than 95%.

中文翻译:

聚变试验设施中氚的监测和回收

摘要 在大型聚变试验设施中,进行氘等离子体实验时,d(d, p)t 反应会产生少量氚。从辐射管理和公众接受的角度出发,为聚变试验装置开发并安装了氚监测和回收系统。在氚监测设备方面,采用氚呼气测试系统对工作人员进行体内剂量评估。有源氚取样器连续运行以监测从烟囱中释放的氚量。在氚回收设备方面,开发了用于等离子体实验的排气脱氚系统(EDS),并安装在聚变试验装置真空泵系统的下游。在氘等离子体实验过程中,所有从真空容器中排出的氚都由 EDS 处理。然后,实现的氚回收率超过 95%。
更新日期:2020-05-05
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