For the first time with the SOLPS-ITER code (using the recently released ‘Wide Grids’ code version 3.2.0), plasma boundary modeling with numerical grids extending to all main chamber surfaces under Q = 10 burning plasma conditions has been performed. This provides main wall fluxes of fuel ions and seeded (neon) impurities, needed for more realistic estimates of wall power fluxes and providing a means to derive tungsten (W) influxes for assessments of impact on burning plasma performance in the recent ITER re-baseline with a full W main wall. Scans (without drifts nor currents activated) have been performed over a range of radial transport coefficients in the far scrape-off layer (SOL). The choice of this range, and in particular the radial variation of the coefficients, is guided by estimates based on the assumption of cross-field filamentary (blobby) transport. In the near SOL the modeling results are close to that of earlier code version. For the far-SOL plasma the results from the code are compared with simple analytical model. The characteristic decay lengths for density and temperatures in the modeling for far SOL agree with analytical estimates. The code modifications required to enable this new wide grid capability for ITER conditions are briefly discussed.