Calculation of Radiation Dose Levels for the Army Pulse Experimental Reactor Assembly

Abstract

Calculations are made to estimate, as a function of distance, the radiation dose levels which would occur during full capacity operation of the ArvW Pulse Reactor Assembly (APRA) scheduled for construction at Aberdeen Proving Ground, Maryland. Calculations of the neutron dose are de by two methods. The first calculation (Method A) is made by utilizing an experimentally determined effective dose mean free path, which probably includes the effect of ground scattering. The second calculation (Method B) is made by utilizing the result of a Monts Carlo calculation of neutron transmission in air. The results of this calculation indicate considerably higher dose levels than indicated by Method A. Experimental data are available which substantiate the result of Method A. The gum dose at distances of interest is found to be unimportant when considered in light of the uncertainty in the neutron dose.