Research
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Liquid
lithium experiments
Among the greatest technological challenges in the creation of a practical fusion power reactor is the development of the material surface that will surround the hot magnetically-confined deuterium-tritium (D-T) plasma fuel. This vacuum chamber wall will be subject to power densities in excess of 25 million watts per square meter from neutrons produced in the D-T fusion reactions, escaping plasma particles, and radiation. Current designs call for a lithium "blanket" to be incorporated into the wall. Fusion neutrons will react with the lithium to produce tritium to be extracted and used as fuel. But the neutrons will also react with the structural materials in the wall itself, producing radioactive isotopes (activation) and possibly causing erosion and loss of structural integrity. Experiments on the Current Drive Experiment-Upgrade (CDX-U) at DOE's Princeton Plasma Physics Laboratory may yield a revolutionary solution to this problem, and, of equal importance, may lead to improved plasma performance. The work, performed in collaboration with DOE's Oak Ridge National Laboratory, DOE's Sandia National Laboratory and the University of California, San Diego, involves studies of the interactions between plasma and liquid lithium. Bob Kaita, who is leading the effort with Dick Majeski, noted, "the use of a flowing liquid lithium wall can potentially eliminate erosion, because the wall is continuously renewed. Furthermore, it may result in a substantial reduction of activation because neutrons will no longer react with materials that stay fixed in a solid wall structure." Kaita went on to point out that lithium can withstand the onslaught of 25 million watts of power per square meter, and it may be able to soak up helium, a by-product of D-T fusion reactions that must be removed from the plasma. Earlier experiments have demonstrated that a conducting wall surrounding the plasma inhibits plasma oscillations and "kinks" that can destroy plasma confinement. Liquid lithium would serve as a conducting wall, and if the lithium flows at rates of 10 to 20 meters per second, its ability to stabilize the plasma may actually improve. Limiter plates are metal surfaces that protrude from the vacuum vessel wall toward the edge of the plasma. Their job is to prevent the plasma from striking the vacuum chamber wall and sputtering impurities, especially heavy metals, into the plasma. Metal atoms soak up energy and radiate it away, causing the plasma temperature to drop. Plasma particles striking the limiter plates are neutralized and return to the plasma where they again become ionized. But this recycling tends to cool the plasma edge, preventing the attainment of beneficial operational modes. A liquid-lithium wall may solve this problem because of its capability for absorbing plasma particles. "For me the most exciting aspect of these experiments is the chance to investigate the behavior of plasmas with a new and different type of boundary. Experience from other experiments all over the world tells us that when we change the wall conditions, we change the plasma contained by the wall," said Dick Majeski. Submitted by DOE's Princeton Plasma Physics Laboratory |
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