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Article summary:
1. JET-ILW tokamak has an all-metal first wall, which is used in the upcoming device, the International Thermonuclear Experimental Reactor (ITER).
2. Experiments on JET-ILW have demonstrated impurity screening by the temperature gradient at the pedestal for the first time in carefully optimised 'hybrid'-scenario H-mode deuterium (D) plasmas.
3. Recent improved understanding of collisional, NC impurity transport has shown that temperature gradient screening is enhanced at low collisionality and by strong toroidal flow.
Article analysis:
The article provides a detailed overview of how high-Z impurities can be screened from plasma in JET-ILW tokamak using a temperature gradient at the pedestal top. The article is well written and provides a comprehensive overview of the topic, including relevant background information and experimental results. The authors provide evidence for their claims with references to relevant research papers and studies.
However, there are some potential biases in the article that should be noted. For example, while the authors discuss how temperature gradient screening can be used to reduce W contamination in plasma, they do not mention any potential risks associated with this method or any other methods of reducing W contamination. Additionally, while they discuss how ELMs can be used to flush impurities from plasma in baseline plasmas, they do not explore any counterarguments or alternative methods for flushing impurities from plasma.
In conclusion, while this article provides a comprehensive overview of how high-Z impurities can be screened from plasma using a temperature gradient at the pedestal top, it does not explore all possible risks associated with this method or alternative methods for flushing impurities from plasma.