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公开(公告)号：US20210350943A1
公开(公告)日：2021-11-11
申请号：US17192748
申请日：2021-03-04
摘要： A confinement chamber for Inertial Confinement Fusion (ICF) may include a closed hohlraum and ICF target wherein the ICF target may comprise a central spherical fuel region, inner shell, outer fuel region, outer shell, and propellant region. A multitude of cylindrical beam channels may penetrate the entire thickness of the hohlraum. At the end of each cylindrical beam channel, where they exit the hohlraum, is a hemispherical cavity. Centered in the curvature of each cavity, and coaxial with each beam channel is a gold foam radiator. By layering materials or grading the density of a material in the propellant region of the closed hohlraum ICF target, the pressure profile on the outer shell may be tailored.
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公开(公告)号：US20190139651A1
公开(公告)日：2019-05-09
申请号：US15980440
申请日：2018-05-15
摘要： In a system and method for utilizing a non-fissile fissionable shell material in a target assembly for Inertial Confinement Fusion (ICF). In one embodiment, the target assembly comprises a central region and a first shell surrounding said central region, wherein said central region receives a fusion fuel mixture and said first shell is a non-fissile fissionable material having a Z greater than 48. By proper configuration of the high-Z shell's fissionable properties, and the timing, the 14 MeV neutrons provide sufficient energy deposition into the shell that it expands at the requisite rate during the implosion, you can get an intrinsically stable implosion.
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公开(公告)号：US20240047087A1
公开(公告)日：2024-02-08
申请号：US17879707
申请日：2022-08-02
摘要： A system and method of enhancing implosion characteristics of an Inertial Confinement Fusion (ICF) target by tailoring the shell such that at the appropriate temperature, the shell allows the energy in the central region to escape. These ICF targets are more efficient than conventional targets in that they utilize the high-Z shell to contain radiation losses from the fusion fuel core. In some embodiments, the shell is designed such that at the appropriate temperature, the shell allows the core radiation to escape. As a result, there is less energy lost. Therefore, the temperature rise in the core is enhanced which aides in the ignition and burn efficiency of the fusion fuel. Further, the ICF targets as described have substantially reduced computational requirements for design and analysis making them more desirable than conventional ICF targets.
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公开(公告)号：US20230374511A1
公开(公告)日：2023-11-23
申请号：US18203549
申请日：2023-05-30
IPC分类号： C12N15/113 , G06F9/48 , G06F9/50 , A61K49/00 , C12Q1/6886
CPC分类号： C12N15/113 , G06F9/4881 , G06F9/5038 , A61K49/0054 , C12N15/1135 , C12Q1/6886 , C12N2320/32 , C12N2310/3515 , G06F9/4887 , G06F9/5083 , G06F2209/501 , G06F9/5027 , C08G2261/1432 , C08G2261/18 , C08G2261/228 , C08G2261/3324 , C08G2261/78 , C12N2310/11 , C12N2310/351 , C12N2310/51 , C12N2320/11
摘要： Inertial Confinement Fusion (ICF) reactor chambers can be designed to contain an ICF target being imploded and capture the resulting energy output from the reaction. The exact amount of energy required to facilitate this implosion depends on the specific target design in use. An ICF target design and implosion mechanism which is more robust against non-uniformities, simpler to analyze and simpler to utilize would be advantageous in achieving practical energy generation. Ideally, the ICF target will be configured to achieve a uniform temperature and density profile when imploding with a variety of parameters not limited to the following: a central region having an areal density (ρr) less than 1 g/cm2 at ignition and approximately 1% of the entire mass to be a material having a Z between 6 and 47 inclusive. Once the parameters of the ICF target are selected, one can easily smooth both the temperature and density profiles in the fusion fuel of non-equilibrium ignition targets without preventing runaway burn or affecting margin parameters such as fall-line greatly.
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公开(公告)号：US11488728B2
公开(公告)日：2022-11-01
申请号：US17179221
申请日：2021-02-18
摘要： A compact, simpler, more economical ICF target chamber and reactor design that maintains a low internal pressure, sub-atmospheric, and very small neutron flux on any pressure bearing vessel or steam generating mechanism. The present invention reduces radiant target emission towards the nearest wall of the hohlraum wall and/or sleeve material so that the radiation from target burn exits the end of the hohlraum through a wall material sufficiently thick to contain the target drive radiation, but becomes transparent to the target emitted radiation. The compact converter contains the energy released by the ICF target and converts it into usable heat to create steam. It also converts the excess neutrons, from the ICF target, into tritium. This is then collected with the unburnt fuel tritium.
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公开(公告)号：US20200176134A1
公开(公告)日：2020-06-04
申请号：US16658915
申请日：2019-10-21
摘要： In a system and method for favorably affecting the Rayleigh-Taylor growth on the interface between the fuel and shell regions of an ICF target. One may increase the ratio of the tritium content to the deuterium content of the fuel or decrease the ratio of the density of the shell to the density of the fuel region. By proper configuration of the ratio between the fuel and shell regions, the Rayleigh-Taylor growth may become more stabilized. This invention would make target manufacturing much simpler and less constrictive, which would in turn decrease the cost.
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公开(公告)号：US20200161007A1
公开(公告)日：2020-05-21
申请号：US15822445
申请日：2017-11-27
摘要： A target assembly for Inertial Confinement Fusion (ICF) achieving a high yield energy output. This high gain target has a low Z fuel/shell region which is lined with a thin layer of a high Z material on the inner surface and then surrounds a low density hotspot region. Adding a thin high Z liner to the inside of the low Z fuel shell has many advantages. As the shell region compresses and heats the central low density hotspot region, the radiation will be contained, and unable to leave the core. This will lower the ignition temperature of target considerably (around a factor of 4). A high Z shell liner may also increase the burn fraction of the fuel as well as increase the areal density (ρr) of the hotspot.
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公开(公告)号：US20200027571A1
公开(公告)日：2020-01-23
申请号：US16191669
申请日：2018-11-15
摘要： A system and method for driving an ICF target with a thermal wave comprising: a target assembly, located inside a hohlraum, comprising a drive region, shell region and central fuel region; wherein said hohlraum comprises one or more laser entrance apertures; wherein said one or more laser entrance apertures are sized according to the shape of said hohlraum and to prevent energy from escaping said hohlraum; a laser assembly to irradiate a laser pulse through said laser entrance apertures; inner walls of said hohlraum to reradiate said laser pulse as x-ray radiation; wherein said x-ray radiation penetrates the target assembly as a thermal wave before any significant hydrodynamic motion occurs within said target assembly during the time in which the laser assembly is active; wherein said drive region is evenly heated to a sufficient temperature to expand in an inward and outward direction; and wherein said shell region is launched into said fuel region to drive said ICF target.
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公开(公告)号：US20220028568A1
公开(公告)日：2022-01-27
申请号：US17179221
申请日：2021-02-18
摘要： A compact, simpler, more economical ICF target chamber and reactor design that maintains a low internal pressure, sub-atmospheric, and very small neutron flux on any pressure bearing vessel or steam generating mechanism. The present invention reduces radiant target emission towards the nearest wall of the hohlraum wall and/or sleeve material so that the radiation from target burn exits the end of the hohlraum through a wall material sufficiently thick to contain the target drive radiation, but becomes transparent to the target emitted radiation. The compact converter contains the energy released by the ICF target and converts it into usable heat to create steam. It also converts the excess neutrons, from the ICF target, into tritium. This is then collected with the unburnt fuel tritium.
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公开(公告)号：US20210272705A1
公开(公告)日：2021-09-02
申请号：US16800203
申请日：2020-02-25
IPC分类号： G21B1/03
摘要： Various configurations for ICF targets and techniques for their utilization are disclosed which may be simpler and more robust than conventional targets. In some embodiments, these targets may operate at a large areal density (ρr), and/or may be imploded primarily by a single strong shock. In some embodiments, the entire volume of a region of fuel may be heated to a desired temperature at once, such that all the fuel mass may participate in the physical processes that may lead to fusion ignition. Targets of this type may be less sensitive to drive non-uniformity and to the temporal profile of driver energy delivery than conventional ICF targets.
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