Abstract Experimental Advanced Superconducting Tokamak (EAST) is capable of operating with long-pulse deuterium plasma, which will generate a lot of radiation such as fusion neutrons, gamma rays and hard X-rays. Since the structure material of the device was activated, work around and inside the tokamak would be limited from a radiation protection point of view after shutdown. Identification of radionuclides and evaluation of dose rate inside the vacuum vessel are needed to develop a guiding principle for radiation protection during maintenance. In this paper, a gamma ray spectrometer based on high purity germanium (HPGe) detector and digitizer was placed inside the vacuum vessel to measure the characteristic gamma ray emission from radionuclides. 7Be, 46Sc, 51Cr, 54Mn, 58Co, 60Co, 59Fe, 88Y, 91Y, 91mNb, 99Mo, 124Sb and 110mAg produced by photonuclear reactions and neutron-induced reactions were identified. The activities of radionuclides was calculated respectively with the uncertainty not exceed 6.05 %. The dose rate for 10 days after shutdown was mainly contributed by 60Co, 58Co, 54Mn, 110mAg, 59Fe, 51Cr, 88Y, 99Mo, 7Be and 124Sb, total dose rate were 3.62 × 10−9 Sv/h(Port E) and 3.40 × 10−9 Sv/h(Port I).

中文翻译：

---

基于伽马射线能谱法的 EAST 停堆放射性初步研究

摘要 实验性先进超导托卡马克（EAST）能够使用长脉冲氘等离子体运行，产生大量辐射，如聚变中子、伽马射线和硬X射线。由于装置的结构材料被激活，在关闭后，从辐射防护的角度来看，托卡马克周围和内部的工作将受到限制。需要识别放射性核素并评估真空容器内的剂量率，以制定维护期间辐射防护的指导原则。在本文中，基于高纯锗 (HPGe) 探测器和数字转换器的伽马射线光谱仪放置在真空容器内，以测量放射性核素的特征伽马射线发射。7Be、46Sc、51Cr、54Mn、58Co、60Co、59Fe、88Y、91Y、91mNb、99Mo、确定了由光核反应和中子诱导反应产生的 124Sb 和 110mAg。放射性核素活度分别计算，不确定度不超过6.05%。停工后10天的剂量率主要由60Co、58Co、54Mn、110mAg、59Fe、51Cr、88Y、99Mo、7Be和124Sb贡献，总剂量率为3.62×10−9 Sv/h（E端口）和3.40 × 10−9 Sv/h（端口 I）。