Excessive power exhaust on divertor target remains a critical challenge for magnetic confinement fusion reactor based on the tokamak concept. If unmitigated, the power received on the divertor target will far exceed the material limit of 5-10MW/m2 in future magnetic fusion reactors such as DEMO. It is widely believed that operating the divertor in the “detached” condition can substantially reduce the target power exhaust, by separating the divertor target from the high-temperature scrape-off layer (SOL) plasmas using a neutral cushion. Common approaches to achieve the detached divertor condition include increasing deuterium fueling rate and injecting radiative impurities.