Chinese language fusion software pushes the previous 100 million levels [Report]



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The experimental advanced superconducting tokamak (EAST), dubbed the "Chinese artificial sun", reached the electron temperature of more than 100 million degrees in nuclear plasma during this four-month experiment this year. It is about seven times larger than the interior of the sun, which is about 15 million degrees C.


The experiment shows that China is making significant progress towards tokamak's production of fusion energy.

The experiment was carried out by the EAST team at Hefei Institute of Physical Science of the Chinese Academy of Sciences (CASHIPS) in cooperation with domestic and international colleagues.

Profibusivity of plasma current density is optimized by effective integration and synergy of four types of heating power: lower hybrid wave heating, electronic cyclotron heating, ion cyclotron resonance heating and neutral ionic heating.

Power injection exceeded 10 MW, while plasma energy increased to 300 kJ, after scientists optimized the connection of various heating techniques. The experiment used advanced plasma control and theory / simulation.

Scientists conducted experiments on plasma equilibrium and instability, retention and transport, plasma wall interactions and physical particle physics that showed a steady-state H-mode operation in steady state with good impurity control, a thermal exhaust system using the ITER-like tungsten redirector.

With operating conditions that are similar to ITER, such as the dominant radio wave heating systems, lower torque and water cooling of the tungsten rectifier, the EAST has achieved a completely non-industrial dynamic balance scenario by extending the efficiency of fusion at high density, high temperature and high constriction.

In the meantime, EAST has used a number of techniques for monitoring local regimes and impurities of tungsten with metal walls, in addition to the active return control of the heat exchanger, to solve the exhaust and exhaust gases, which is crucial for high performance steady state.

Operating scenarios, including stable high-performance H-modes and electronic temperatures of more than 100 million degrees in the East, contributed to ITER, the Chinese reactor Fusion Engineering Fusion Engineering (CFETR) and DEMO.

These results provide key data for the validation of heat exhaust, transport and current drive models. They also increase confidence in the CFETR fusion efficacy forecast.

Currently, the CFETR physics plan focuses on the optimization of a third large-radius evolution machine with a 7 m radius, a smaller radius of 2 m, a magnetic field of magnets 6.5-7 Tesla and a plasma flow of 13 MA.

At the end of this year, a new national mega science project – a comprehensive research resource – will be launched to support the development of CFETR engineering and the future DEMO.

This new project will stimulate the development of test modules of tritium blankets, superconducting technology, reactor heating and actuator drives and resources and propulsion materials.

EAST is the first complete superconductive tokamak with a non-circular cross-section in the world. The project was designed and manufactured by China with an emphasis on key scientific issues related to the use of fusion power. Since its inception in 2006, the EAST has become a fully open test laboratory where the global fusion community can run steady state operations and ITER-related physics research.

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The experimental advanced superconducting tokamak (EAST), dubbed the "Chinese artificial sun", reached the electron temperature of more than 100 million degrees in nuclear plasma during this four-month experiment this year. It is about seven times larger than the interior of the sun, which is about 15 million degrees C.

The experiment shows that China is making significant progress towards tokamak's production of fusion energy.

The experiment was carried out by the EAST team at Hefei Institute of Physical Science of the Chinese Academy of Sciences (CASHIPS) in cooperation with domestic and international colleagues.

Profibusivity of plasma current density is optimized by effective integration and synergy of four types of heating power: lower hybrid wave heating, electronic cyclotron heating, ion cyclotron resonance heating and neutral ionic heating.

Power injection exceeded 10 MW, while plasma energy increased to 300 kJ, after scientists optimized the connection of various heating techniques. The experiment used advanced plasma control and theory / simulation.

Scientists conducted experiments on plasma equilibrium and instability, retention and transport, plasma wall interactions and physical particle physics that showed a steady-state H-mode operation in steady state with good impurity control, a thermal exhaust system using the ITER-like tungsten redirector.

With operating conditions that are similar to ITER, such as the dominant radio wave heating systems, lower torque and water cooling of the tungsten rectifier, the EAST has achieved a completely non-industrial dynamic balance scenario by extending the efficiency of fusion at high density, high temperature and high constriction.

In the meantime, EAST has used a number of techniques for monitoring local regimes and impurities of tungsten with metal walls, in addition to the active return control of the heat exchanger, to solve the exhaust and exhaust gases, which is crucial for high performance steady state.

Operating scenarios, including stable high-performance H-modes and electronic temperatures of more than 100 million degrees in the East, contributed to ITER, the Chinese reactor Fusion Engineering Fusion Engineering (CFETR) and DEMO.

These results provide key data for the validation of heat exhaust, transport and current drive models. They also increase confidence in the CFETR fusion efficacy forecast.

Currently, the CFETR physics plan focuses on the optimization of a third large-radius evolution machine with a 7 m radius, a smaller radius of 2 m, a magnetic field of magnets 6.5-7 Tesla and a plasma flow of 13 MA.

At the end of this year, a new national mega science project – a comprehensive research resource – will be launched to support the development of CFETR engineering and the future DEMO.

This new project will stimulate the development of test modules of tritium blankets, superconducting technology, reactor heating and actuator drives and resources and propulsion materials.

EAST is the first complete superconductive tokamak with a non-circular cross-section in the world. The project was designed and manufactured by China with an emphasis on key scientific issues related to the use of fusion power. Since its inception in 2006, the EAST has become a fully open test laboratory where the global fusion community can run steady state operations and ITER-related physics research.

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