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Design and analysis of the radiation shield and safety system for HT-7U tokamak

机译:HT-7U托卡马克辐射防护屏及安全系统设计与分析

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摘要

The design of the radiation shield and safety system for the HT-7U fusion experimental device is presented in this contribution. An inner shield and an outer shield are considered in the shield design. Calculations and analyses have been done using 3D MCNP/4C models for the neutron spectrum and with the inventory code FISPACT for activation calculation in order to estimate the dose rate to workers after one pulse operation of the device. In addition, a computer system for radiation protection and control based on Controller Area Network has been developed in order to protect staff and publics from the radiation of neutrons and γ during and after the operation of the HT-7U device. The safety system has the advantages of multi-master protocol, real-time capability, error correction, long communication distance and high noise immunity etc.
机译:该文稿介绍了用于HT-7U融合实验设备的辐射防护屏和安全系统的设计。屏蔽设计中考虑了内部屏蔽和外部屏蔽。已经使用用于中子谱图的3D MCNP / 4C模型和用于激活计算的库存代码FISPACT进行了计算和分析,以便在设备进行一次脉冲操作后估计对工作人员的剂量率。另外,已经开发了基于控制器局域网的辐射防护和控制计算机系统,以保护工作人员和公众在HT-7U设备运行期间和之后免受中子和γ辐射。该安全系统具有多主协议,实时能力,纠错能力强,通信距离长,抗干扰能力强等优点。

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