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Since 1964, the Health Physics Research Reactor (HPRR) at the Oak Ridge National Laboratory has been used to simulate nuclear excursions to allow intercomparisons of accident dosimetry systems. Generally, activation foils or threshold-activation foils are used to measure the neutron fluence. Usually, data from these detectors are used to provide the neutron dose and the general shape of the neutron energy spectrum. However, some participants have used an iterative technique to calculate a spectral distribution to fit the experimental results. A calculational study was begun to provide the HPRR neutron spectrum for three typical accident exposure conditions. Results of these calculations are compared with spectra derived from the use of several dosimeters under actual exposure conditions at the HPRR. Also included in the results of the calculation were neutron dose distributions as a function of distance from the reactor. These results are compared with the results of measurements performed during the Intercomparison Study of 1971.

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