scholarly journals Use of an ‘Inter-Linked^|^apos; Central Solenoid for Plasma Current Ramp-Up in a Tokamak Fusion Reactor

2013 ◽  
Vol 8 (0) ◽  
pp. 1205007-1205007 ◽  
Author(s):  
Makoto NAKAMURA ◽  
Kenji TOBITA ◽  
Hiroyasu UTOH
Keyword(s):  
Fusion Reactor ◽  
Plasma Current ◽  
Tokamak Fusion Reactor ◽  
Current Ramp

scholarly journals Cost Assessment of a Tokamak Fusion Reactor with an Inventive Method for Optimum Build Determination

Energies ◽  
2021 ◽  
Vol 14 (20) ◽  
pp. 6817
Author(s):  
Gahyung Jo ◽  
Jae-Min Kwon ◽  
Ara Cho ◽  
Hyun-Kyung Chung ◽  
Bong-Guen Hong
Keyword(s):  
Fusion Reactor ◽  
Cost Model ◽  
Minimum Cost ◽  
System Size ◽  
Capital Cost ◽  
Plasma Current ◽  
Tokamak Fusion Reactor ◽  
Wide Range ◽  
Major Radius ◽  
The Impact

An inventive method was applied to determine the minimum major radius, R0, and the optimum build of a tokamak fusion reactor that simultaneously meets all physics, engineering, and neutronics constraints. With a simple cost model, tokamak systems analyses were carried out over ranges of system parameters to find an optimum build of a tokamak fusion reactor at minimum cost. The impact of a wide range of physics parameters and advanced engineering elements on costs were also addressed. When a central solenoid was used to ramp up a plasma current, design solutions with a cost of electricity (COE) between 109 and 140 mills/kWh, direct capital cost between 5000 and 6000 M/USD, and net electric power, Pe between 1000 and 1600 MW could be found with a minimum R0 between 6.0 and 7.0 m, and fusion power, Pfusion between 2000 and 2800 MW. When the plasma current was driven by a non-inductive external system, the system size and costs could be reduced further; a COE between 98 and 130 mills/kWh, direct capital cost between 4000 and 5000 M$, and Pe between 1000 and 1420 MW could be found with a minimum R0 between 5.1 and 6.7 m, and Pfusion between 2000 and 2650 MW.

Progress Toward a Tokamak Fusion Reactor

Physics Today ◽  
1992 ◽  
Vol 45 (1) ◽  
pp. 22-30 ◽  
Author(s):  
J. Geoffrey Cordey ◽  
Robert J. Goldsron ◽  
Ronald R. Parker
Keyword(s):  
Fusion Reactor ◽  
Tokamak Fusion Reactor

Prototype tokamak fusion reactor based on SiC/SiC composite material focusing on easy maintenance

2000 ◽  
Vol 48 (3-4) ◽  
pp. 271-279 ◽  
Author(s):  
S Nishio ◽  
S Ueda ◽  
R Kurihara ◽  
T Kuroda ◽  
H Miura ◽  
...  
Keyword(s):  
Composite Material ◽  
Fusion Reactor ◽  
Tokamak Fusion Reactor

scholarly journals ORNL TNS Program: Plasma Engineering Considerations and Innovations for a Medium Field Tokamak Fusion Reactor

1977 ◽  
Author(s):  
Y-K. M. Peng ◽  
S. E. Attenberger ◽  
W. A. Houlberg ◽  
A. T. Mense ◽  
J. A. Rome ◽  
...  
Keyword(s):  
Fusion Reactor ◽  
Tokamak Fusion Reactor

scholarly journals Natural fueling of a tokamak fusion reactor

2010 ◽  
Vol 17 (4) ◽  
pp. 040701 ◽  
Author(s):  
Weigang Wan ◽  
Scott E. Parker ◽  
Yang Chen ◽  
Francis W. Perkins
Keyword(s):  
Fusion Reactor ◽  
Tokamak Fusion Reactor

The ITB dynamics controlled by internal kink modes on HL-2A tokamak

2021 ◽  
Author(s):  
Xiaoxue He ◽  
Longwen Yan ◽  
Deliang Yu ◽  
Wei Chen ◽  
Liming Yu ◽  
...  
Keyword(s):  
High Performance ◽  
Fusion Reactor ◽  
Rotation Velocity ◽  
Plasma Current ◽  
Ion Temperature ◽  
Lower Plasma ◽  
Transport Barriers ◽  
Internal Transport Barriers ◽  
Foot Position ◽  
Internal Transport

Abstract The active control of internal transport barriers (ITBs) is an important issue to achieve high performance plasma in a fusion reactor. A critical challenge of ITB control is to increase the ITB position. The ITBs with internal kink modes (IKMs), such as fishbone instability and long-live mode (LLM) with mode number of m/n = 1/1 are frequently observed on HL-2A tokamak in neutral beam heated discharges. The correlation of fishbone instability/LLM with ITBs is analyzed in order to extend the ITB radius. It has been revealed that fishbone instability and LLM are often excited after the ITB formation. Therefore, fishbone instability and LLM play no role in triggering ITBs on HL-2A tokamak. On the other hand, they may slow down the outward radial expansion and then shrink the foot position of ITB, and damp the gradient growth of ion temperature and rotation velocity. Since the perturbation of LLM is weaker than that of fishbone instability, the shrinking effect of ITB foot and braking effect on gradient growth are slighter than those of fishbone instability. Compared with the LLM, fishbone instability routinely appears in plasmas with lower density, higher heating power and lower plasma current. In addition, large ITBs without IKMs are also discussed on HL-2A tokamak. The large ITB is the largest one, the fishbone ITB is the strongest one and the LLM ITB is the widest one in three ITBs, where the ‘large’, ‘strong’ and ‘wide’ qualifications correspond to ITB position ρITB, the normalized temperature gradient R/LT, and its width W/a. Therefore, the large ITB position may be obtained if the IKMs are effectively controlled in a tokamak.

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