用HT-7造句子，“HT-7”造句

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

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

12、實驗中將純鎢樣品放入HT-7託卡馬克的刮削層中，以研究等離子體與純鎢表面的作用。

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

18、介紹了振動時效技術在HT-7U超導託卡馬克核聚變大底板、真空裝置等能源工程中的應用。

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

5、Experimental study of large power lower hybrid current drive on 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.

14、分析了HT-7託卡馬克壁處理前後歐姆放電時的自舉電流佔總等離子體電流比例的變化情況。

19、文章分析了由等離子體電流和真空室感應電流在HT-7U裝置環向場超導磁體中產生的渦流損耗。

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

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.

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.

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

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.

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

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

13、實驗中通過前級PIN開關控制不同的低雜波輸出模式，滿足了HT-7裝置相應實驗對低雜波的要求。

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