The target fuel depletion and energy gain of inertial confinement fusion （ICF） for uniform spherical target of D-SHe advanced fuel compressed by high power laser-beam have been derived and calculated in this article...The target fuel depletion and energy gain of inertial confinement fusion （ICF） for uniform spherical target of D-SHe advanced fuel compressed by high power laser-beam have been derived and calculated in this article. Our numerical calculations show that if only the approximation of small internal energy of central spark and high inertial confinement parameter Hr = ρRF is valid for typical efficiency parameters of reactor system, the net fusion energy output can be possible for ICF of D-3He target. Inversely, under the approxi- mation of large internal energy of central spark and low HF it will not be possible to get net fusion energy output for ICF of D-^3He target. Hereby, an indirect proof of the scientific basis of fast ignition（FI） philosophy has been provided as a matter of fact.展开更多
The magnetic fusion reactor using the advanced D-3He fuels has the advantage of much less-neutron productions so that the consequent damages to the first wall are less serious. If the establishment of this kind of rea...The magnetic fusion reactor using the advanced D-3He fuels has the advantage of much less-neutron productions so that the consequent damages to the first wall are less serious. If the establishment of this kind of reactor becomes realistic, the exploration of 3He on the moon will be largely motivated. Based on recent progresses in the spherical torus (ST) research, we have physically designed a D-3He fusion reactor using the extrapolated results from the ST experiments and also the present-day tokamak scaling. It is found that the reactor size significantly depends on the wall reflection coefficient of the synchrotron radiation and of the impurity contaminations. The secondary reaction between D-D that promptly leads to the D-T reaction producing 14 MeV neutrons is also estimated. Comparison of this D-3He ST reactor with the D-T reactor is made.展开更多
基金Supported by National Natural Science Foundation of China（Special Exploring Foundation Preject, 2003AA84ta01 ）
文摘The target fuel depletion and energy gain of inertial confinement fusion （ICF） for uniform spherical target of D-SHe advanced fuel compressed by high power laser-beam have been derived and calculated in this article. Our numerical calculations show that if only the approximation of small internal energy of central spark and high inertial confinement parameter Hr = ρRF is valid for typical efficiency parameters of reactor system, the net fusion energy output can be possible for ICF of D-3He target. Inversely, under the approxi- mation of large internal energy of central spark and low HF it will not be possible to get net fusion energy output for ICF of D-^3He target. Hereby, an indirect proof of the scientific basis of fast ignition（FI） philosophy has been provided as a matter of fact.
基金The project supported by the National Nature Science Foundation of China (No. 10375018)
文摘The magnetic fusion reactor using the advanced D-3He fuels has the advantage of much less-neutron productions so that the consequent damages to the first wall are less serious. If the establishment of this kind of reactor becomes realistic, the exploration of 3He on the moon will be largely motivated. Based on recent progresses in the spherical torus (ST) research, we have physically designed a D-3He fusion reactor using the extrapolated results from the ST experiments and also the present-day tokamak scaling. It is found that the reactor size significantly depends on the wall reflection coefficient of the synchrotron radiation and of the impurity contaminations. The secondary reaction between D-D that promptly leads to the D-T reaction producing 14 MeV neutrons is also estimated. Comparison of this D-3He ST reactor with the D-T reactor is made.
