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Calculation of low-energy neutron flux in the atmosphere by the<i>S</i><sub><i>n</i></sub>method
65
Citations
17
References
1963
Year
Upper AtmosphereEngineeringNuclear PhysicsCosmic-ray NeutronsNuclear DataNeutron FluxReactor PhysicsEarth ScienceAtmospheric ScienceLow-energy Neutron FluxEnergy GroupHigh-energy Nuclear ReactionPhysicsNeutron SourceRadiation TransportCosmic RayNeutron TransportSpace WeatherNuclear EngineeringNuclear EnergyNatural Sciences
The transport equation pertaining to cosmic-ray neutrons in the atmosphere was solved for neutron flux by means of the numerical multigroup Sn method. Flux values were obtained at geomagnetic latitude 57°N as a function of altitude and energy group in the range from thermal to 20 Mev. These results, and continuous neutron flux distributions over energy determined from them, are presented for several representative altitudes. On the basis of the fluxes and appropriate neutron cross sections, averaged world rates for production of carbon 14 and tritium by neutron absorption processes in the atmosphere were calculated to be 2.1 atoms C14 cm−2 sec−1 and 0.07 atom T cm−2 sec−1. All results obtained are compared with other results.
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