HT-7造句

1、Data Acquisition of Realtime EFIT Programme in HT-7 Tokamak

2、Study of the Electron Heatingin LHCD Plasma in HT-7;

3、Measurements of Diamagnetism and Energy Confinement Time Scaling in HT-7 Superconducting Tokamak;

4、Design and implementation of timing trigger module in the integrator on HT-7

5、Experimental study of large power lower hybrid current drive on HT-7 tokamak

6、Study of the Front of the ECE Radiometer on HT-7 Tokamak

7、Application of Low Pass Filtering PID Control Algorithm for Plasma Density Control System in HT-7 Tokamak

8、Investigation on the generation of runaway electrons on the HT-7 tokamak with low hybrid current drive

9、The Study of Reduced Activation Ferritic/martensitic Steels and Tungsten Irradiated by Plasma in HT-7 Tokamak;

10、A power supply system for diagnostic neutral beam on the HT-7 Tokamak was developed. Its logic control system based on S7-300 PLC was described.

11、In the experiment, samples of pure tungsten were placed in the scrape-off layer of HT-7 tokamak to study the interaction between plasma and the surface of samples.

12、实验中将纯钨样品放入HT-7托卡马克的刮削层中，以研究等离子体与纯钨表面的作用。

13、实验中通过前级PIN开关控制不同的低杂波输出模式，满足了HT-7装置相应实验对低杂波的要求。

14、分析了HT-7托卡马克壁处理前后欧姆放电时的自举电流占总等离子体电流比例的变化情况。

15、Real-Time Control System of Plasma Shape and Position in HT-7U;

16、The article introduces the principle of the quench detection system and the characters of the quench signal in the HT-7U CS model coil experiment.

17、The eddy current losses in the toroidal field superconducting magnet of the HT-7U tokamak, produced by plasma current and the eddy currents on the vacuum vessel, are analyzed.

18、介绍了振动时效技术在HT-7U超导托卡马克核聚变大底板、真空装置等能源工程中的应用。

19、文章分析了由等离子体电流和真空室感应电流在HT-7U装置环向场超导磁体中产生的涡流损耗。