Neutron capture in the atmosphere from high altitude point sources

by J. I. Marcum

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A presentation of results for the spatial and time-dependence of neutron capture from a representative fission weapon spectrum and a 14 Mev monoenergetic source at altitudes of 10 km to 48.3 km in the real atmosphere. The solutions have been obtained by the use of the RAND Monte Carlo Neutron Transport Code. A reasonable approximation to the energy deposition may be simply obtained by assuming that all of the energy is locally deposited. If more precise results are desired, the gamma ray component of the thermal capture process should be treated as a further radiation transport problem.

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