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Fusion Reactor and Fusion Reactor Materials— Target Fuel Depletion Fraction and Energy Gain of Inertial Confinement Fusion with D-^3He Advanced Fuel
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作者 DENG Baiquan FENG Kaiming 《Southwestern Institute of Physics Annual Report》 2004年第1期85-88,共4页
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
关键词 D-^3He advanced fuel target ICF fuel depletion and energy gain
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