  This paper analyzes the neutral fluxes in the divertor region of the W7-X
standard configuration for different input powers, both under attached and
detached conditions. The performed analysis is conducted through EMC3-EIRENE
simulations. They show the importance of the horizontal divertor to generate
neutrals, and resolve the neutral plugging in the divertor region. Simulations
of detached cases show a decrease in the number of generated neutrals compared
to the attached simulations, in addition to a higher fraction of the ion flux
arriving on the baffles during detachment. As the ionization takes place
further inside the plasma during detachment, a larger percentage of the
generated neutral particles leave the divertor as neutrals. The leakage in the
poloidal and toroidal direction increases, just as the fraction of collected
particles at the pumping gap. The fraction of pumped particles increases with a
factor two, but stays below one percent. This demonstrates that detachment with
the current target geometry, although it improves the power exhaust, is not yet
leading to an increased particle exhaust.
