Reduced neutron emission target for fusion energy generation

Abstract

A fuel target device for an inertial confinement fusion process. The device comprises a center region is comprising a first fuel layer of deuterium-tritium-lithium ((DT)(1-x)Lix, 0<x<0.5) fuel characterized by a higher or equal ignition temperature in comparison with a lowest ignition temperature of deuterium-tritium (DT). The device comprises a second fuel layer of deuterium-tritium (DT) fuel characterized by the lowest ignition temperature is surrounding the center region, and a third fuel layer comprising an outer region of a pure hydrogen (H2) or a proton rich boron (pyB(1-y)11, 1>y>0.5) material is surrounding the deuterium-tritium (DT) fuel such that the deuterium-tritium (DT) fuel is sandwiched between the deuterium-tritium-lithium ((DT)(1-x)Lix, 0<x<0.5) fuel and the pure hydrogen or proton rich boron (pyB(1-y)11, 1>y>0.5) material.

Dependencies are inferred from the claim text.