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Hu C.,CAS Hefei Institutes of Physical Science
Plasma Science and Technology | Year: 2012

The neutral beam injection (NBI) system is one of the most important auxiliary plasma heating and current driving methods for fusion device. A high power ion beam of 3 MW with 80 keV beam energy in 0.5 s beam duration and a long pulse ion beam of 4 s with 50 keV beam energy ion beam extraction were achieved on the EAST neutral beam injector on the test-stand. The preliminary results show that the EAST-NBI system was developed successfully on schedule. Source


Hu C.,CAS Hefei Institutes of Physical Science
Plasma Science and Technology | Year: 2013

Neutral beam injection (NBI) is recognized as one of the most effective means for plasma heating. A 100 s long pulse neutral beam with 30 keV beam energy, 10 A beam current and a 100 s long pulse modulating neutral beam with 50 keV beam energy, 16 A beam current were achieved in the EAST neutral beam injector on the test-stand. The preliminary results suggest that EAST-NBI system initially possess the ability of long pulse beam extraction. Source


Wu Z.,CAS Hefei Institutes of Physical Science
Angewandte Chemie - International Edition | Year: 2012

Unexpected: Anti-galvanic reduction (AGR), that is, metal ions are reduced by more-noble metals, was found in small thiolated gold (see figure) and silver nanoparticles! These findings are not only unexpected considering the classic galvanic theory, but also provide a facile and mild method to make alloys on the nanoscale or tune the compositions, structures, and properties of nanostructures that are otherwise difficult to obtain. Copyright © 2012 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim. Source


Hu C.,CAS Hefei Institutes of Physical Science
Plasma Science and Technology | Year: 2015

As one of the most effective methods for plasma heating, a neutral beam injector (NBI) achieved plasma heating and current driving for the first time in EAST 2014 experimental campaign. According to the research plan of the EAST physics experiment, the first NBI (EAST-NBI-1) has been built and become operational in 2014. In this article, the latest experiment results of EAST-NBI-1 are reported as follows: (1) EAST achieves H-mode plasma in the case of NBI heating alone, (2) EAST achieves 22 s long pulse stable H-mode plasma in the case of simultaneous NBI and lower hybrid wave (LHW) heating. The measurement data show that the loop voltage decreased and the plasma stored energy increased obviously. The results indicate that EAST-NBI-1 has achieved plasma heating and current driving, and thus lays a foundation for the construction of EAST-NBI-2, which will be built in a few months this year. © 2015, Institute of Physics Publishing. All rights reserved. Source


Hu C.,CAS Hefei Institutes of Physical Science
Plasma Science and Technology | Year: 2012

Neutral beam injection (NBI) system with two neutral beam injections will be constructed on the Experimental Advanced Superconducting Tokamak (EAST) in two stages for high power auxiliary plasmas heating and non-inductive current drive. Each NBI can deliver 2∼4 MW beam power with 50∼80 keV beam energy in 10∼100 s pulse length. Each elements of the NBI system are presented in this contribution. Source

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