Neutron and gamma-ray tissue kerma and scalar spectrum measurements have been made at the Army Pulse Radiation Division (APRD), Aberdeen Proving Ground, to 1.6 km in air-over-ground geometry from a fission source and are compared to state-of-the-art transport calculations. Measurements have been made by the APRD staff as well as German, Canadian, and French scientists. A variety of integral detectors and differential spectrometers were used. Agreement among the various groups ranges from good to excellent. Calculations have been made in support of shielding programs and in connection with the Hiroshima-Nagasaki dose reevaluation effort. The DOT transport calculations have been performed at the Lawrence Livermore and Oak Ridge National Laboratories, the Defence Research Establishment, Ottawa, and at Science Applications, Inc. Monte Carlo calculations have been performed at Los Alamos National Laboratory. The calculations are generally consistent. Average calculated-to-measured kerma ratios range from 0.83 to 1.27. Calculated-to-measured neutron flux ratios vary from ∼0.6 near 1 keV and ∼0.8 near 5 MeV to ∼1.7 near 0.8 MeV. These spectral differences tend to cancel when determining tissue kerma, raising the possibility that some of the agreement in kerma may be fortuitous. Sources of possible discrepancies are discussed