Simple Method to Calculate Neutron Energy Deposition in ICF Targets (English)

1986
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In most ICF-target simulation calculations alpha 's and other charged particles are supposed to be reabsorbed in the plasma whereas neutrons are often allowed to escape without interaction. However, in reactor size targets neutrons lose about the same amount of energy in the DT-fuel as alpha -particles and can considerably influence the burn characteristics of the target. In the present paper a simple method to account for neutron-fuel interaction is presented. Results are compared with Monte-Carlo and S/sub N/ transport calculations. The effect of neutron energy deposition in the fuel on the performance is shown on the 4 mg DT-target of the HIBALL reactor. (ERA citation 12:022005)