A new plasma escape mechanism could protect fusion vessels from excessive heat

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This still image from a new simulation shows how plasma from the pedestal region is connected to the divertor plasma region via the so-called final confinement surface. The long and thin lobes fluctuate in time and space. Credit: (Simulation) Seung-Hoe Ku/Princeton Plasma Physics Laboratory on DOE’s Summit computer at Oak Ridge National Laboratory; (Visualization) Dave Pugmire and Jong Youl Choi / Oak Ridge National Laboratory

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This still image from a new simulation shows how plasma from the pedestal region is connected to the divertor plasma region via the so-called final confinement surface. The long and thin lobes fluctuate in time and space. Credit: (Simulation) Seung-Hoe Ku/Princeton Plasma Physics Laboratory on DOE’s Summit computer at Oak Ridge National Laboratory; (Visualization) Dave Pugmire and Jong Youl Choi / Oak Ridge National Laboratory

The raging exhaust heat generated by a melt plasma in a commercial-scale reactor may not be as damaging to the ship’s innards as once thought, according to researchers at the U.S. Department of Energy’s (DOE) Princeton Plasma Physics Laboratory (PPPL). ), Oak Ridge. National Laboratory and the ITER Organization (ITER).

“This discovery fundamentally changes the way we think about how heat and particles travel between two crucial regions at the edge of a plasma during fusion,” said Choongseok Chang, PPPL’s ​​Managing Principal Research Physicist, who led the team. researchers behind the discovery. A new article describing their work was recently published in the journal Nuclear fusionin response to previous publications on this subject.

To achieve fusion, temperatures in a tokamak (the doughnut-shaped device that holds the plasma) must rise above 150 million degrees Celsius. That is ten times hotter than the center of the sun. Containing something that hot is a challenge, even though the plasma is largely kept away from the interior surfaces using magnetic fields. These fields keep most of the plasma confined in a central region known as the core, forming a doughnut-shaped ring.

However, some particles and heat escape from the trapped plasma and strike the material facing the plasma. New findings from PPPL researchers suggest that particles escaping from the nuclear plasma in a tokamak collide with a larger area of ​​the tokamak than once thought, significantly reducing the risk of damage.

Previous research based on physics and experimental data from contemporary tokamaks suggested that the exhaust heat would concentrate on a very narrow band along a section of the tokamak wall known as the divertor plates. The divertor is intended to remove exhaust heat and particles from the burning plasma and is critical to the performance of a tokamak.


The experimental ITER tokamak will have a divertor that runs in a ring around the bottom of the tokamak chamber. In the image above, the divertor is highlighted in yellow. Credit: ITER Organization

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The experimental ITER tokamak will have a divertor that runs in a ring around the bottom of the tokamak chamber. In the image above, the divertor is highlighted in yellow. Credit: ITER Organization

“If all this heat hits this narrow area, this part of the divertor plate will be damaged very quickly,” says Chang, who works in the PPPL theory department. “It can lead to frequent downtime. Even if you replace just this part of the machine, it won’t be quick.”

The problem has not stopped the operation of existing tokamaks, which are not as powerful as those that will be needed for a commercial-scale fusion reactor. However, in recent decades there has been significant concern that a commercial-scale device would create plasmas so dense and hot that the divertor plates could be damaged. One proposed plan involved adding impurities to the edge of the plasma to radiate away the energy of the escaping plasma, reducing the intensity of the heat hitting the divertor material, but Chang said this plan is still a challenge used to be.

Simulating the escape route

Chang decided to investigate how the particles escaped and where the particles would end up on a device like ITER, the multinational fusion facility being built in France. To do this, his group created a plasma simulation using a computer code known as X-Point Included Gyrokinetic Code (XGC). This code is one of many developed and maintained by PPPL and used for fusion plasma research.

The simulation showed how plasma particles traveled through the magnetic field surface, which was intended as the boundary separating the confined plasma from the non-confined plasma, including the plasma in the divertor region. This magnetic field surface – generated by external magnets – is called the final confinement surface.


This visualization shows how the pedestal plasma crosses the white dotted lines, representing a separation point between the pedestal plasma and the divertor plasma. The orange and yellow represent the plasma. Credit: Dave Pugmire and Jong Youl Choi/Oak Ridge National Laboratory

A few decades ago, Chang and his colleagues discovered that charged particles, known as ions, crossed this barrier and hit the divertor plates. They later discovered that these escaping ions caused the heat load to be concentrated on a very narrow area of ​​the divertor plates.

A few years ago, Chang and his colleagues discovered that plasma turbulence can allow negatively charged particles called electrons to pass through the final confinement surface and increase the heat load on the divertor plates in ITER by ten times. However, the simulation still assumed that the final confinement surface was not disturbed by the plasma turbulence.

“In the new paper, we show that the final confinement surface is strongly disturbed by the plasma turbulence during fusion, even in the absence of disturbances caused by external coils or abrupt plasma instabilities,” Chang said. “A good final confinement surface does not exist because of the crazy, turbulent magnetic surface disturbances called homoclinic tangles.”

Chang said the simulation showed that electrons connect the edge of the main plasma to the divertor plasmas. The path of the electrons as they follow the path of these homoclinic tangles expands the heat impact zone 30% more than the previous estimate of its width, based on turbulence alone.

He explained: “This means that it is even less likely that the divertor surface will be damaged by the exhaust heat combined with the radiative cooling of the electrons from injection of impurities into the divertor plasma. The research also shows that the turbulent homoclinic tangles are more likely to experience abrupt instabilities at the edge of the plasma, as this weakens their driving force.

“The final confinement surface in a tokamak should not be trusted,” Chang said. “But ironically, it can improve fusion performance by reducing the chance of damage to the divertor surface under steady-state operation and eliminating the transient burst of plasma energy to the divertor surface due to the sudden plasma instabilities, which are two of the most performance-limiting problems .in future commercial tokamak reactors.”

More information:
C. S. Chang et al., The role of turbulent separatrix tangle in the improvement of the integrated pedestal and heat exhaust problem for stationary tokamak fusion reactors, Nuclear fusion (2024). DOI: 10.1088/1741-4326/ad3b1e

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