CALCULATION OF RADIATION DOSE LEVELS FOR THE ARMY PULSE EXPERIMENTAL REACTOR ASSEMBLY
ARMY BALLISTIC RESEARCH LAB ABERDEEN PROVING GROUND MD
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Calculations are side to estimate, as a function of distance, the radiation dose levels which would occur during full capacity operation of the Army Pulse Reactor Assembly APRA scheduled for construction at Aberdeen Proving Ground, Maryland. Calculations of the neutron dose are made 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 Monte 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 gamma dose at distances of interest is found to be unimportant when considered in light of the uncertainty in the neutron dose.
- Nuclear Power Plants and Fission Reactor Engineering
- Radioactivity, Radioactive Wastes and Fission Products