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1. NEUTRONICS DESIGN OF A GAS COOLED TOKAMAK COMMERCIAL BREEDER.

2. BURNUP CALCULATION FOR A TOKAMAK COMMERCIAL HYBRID REACTOR.

3. Optimization analysis of tokamak plasma fuelling with the supersonic molecular beam ( SMB ) has been made.

4. Inside the Tokamak are a series of magnets powered by the plant.

5. Deputy Director of Tokamak Division , Institute of Plasma Physics, Chinese Academy of Sciences.

6. ITER(International Thermonuclear Experimental Reactor) is a planning international Tokamak reactor designed to demonstrate the feasibility of the full dimensions controlled nuclear fusion technology.

7. A kind of photo diode detector used in Tokamak visible light measurement was developed.

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8. The Tokamak equilibrium fitting numerical calculation code EFIT is modified to study the MUD ( magnetohydrodynamics ) equilibrium in an EAST device.

9. Assuming that the transport operator is linear, the tokamak particle transport equations are systematically analyzed.

10. In Tokamak device, the behavior of plasma is difficult to analyze and control.

11. Basic principle ofthe controlled nuclear fusion and the Tokamak device used for nuclear fusion reaction are presented in brief.

12. ITER is what is known as a tokamak, a doughnut-shaped device invented in Russia at about the same time Zeta was active.

13. Fusion funding remains steady, but with the money now divided mostly between the two leading machines, the tokamak and mirror-fusion.

14. The table shows the steady progress we have made with tokamaks over the past quarter of a century.

15. In this paper, electron beam physics, equilibrium of plasma in Tokamak under electron injection and physical problems involved in the electron injector were analytically studied.

16. For safe reason, an overall check and analysis of cryogenic mechanics property for EAST Tokamak composite insulators is needed.

17. A set of 5-channel heterodyne receiver system for measuring the ECE signals of the HT-6B tokamak plasma is described.

18. An application of this system has been demonstrated succeed on HT - 7 tokamak in 2005.

19. The technology of vibratory stress relief(VSR) used in energy engineering, such as HT-7U nuclear fusion superconducting Tokamak massive base plate and vacuum vessel was introduced.

20. Accordingly, the effects of the main classes of the stray field in Tokamak devices are analysed.

21. The horizontal stray field and its optimized dynamic compensation in the HL-1 tokamak have been studied both experimentally and theoretically.

22. The transient space process of molecular in a toroidal vacuum chamber of tokamak device during pulse puffing gas has been simulated by Monte-Carlo method.

23. In this paper, the fuel gas and propellent system of "in site" Pellet injector used in beforehand experiment and Pellet fueling experiment in HL-1 Tokamak has been introduced.

24. The time - resolved neutron flux density measurement system on HT - 7 Tokamak is presented in the paper.

25. Thomson scattering diagnostic system with multi-pulse Nd glass laser is described for measuring time-space evolution of electron temperature on the HL-1M tokamak.

26. It is very important that spectrum measurement of D - D and D - T fusion neutron in large Tokamak.

27. In this paper, the relationship between the low frequency drift wave and the empirical law of anomalous transport in Tokamak the pseudo-classical diffusion is discussed.

28. The data acquisition and processing system and automatic monitor system based on the data communication of multimicrocomputers for the physics experiments of HL-1 tokamak are described.

29. An eigenmode equation of ion temperature gradient driven instability in a tokamak plasma with negative magnetic shear is solved numerically by the shooting method.

30. As a candidate plasma facing material, Graphites are widely used as the armor material for first wall and divertor plate in current tokamak devices.