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1. 发明授权

US11621098B2 Methods of energy generation from a thorium molten salt system 有权
公开(公告)号：US11621098B2
公开(公告)日：2023-04-04
申请号：US17444483
申请日：2021-08-05
申请人： Texas Thorium LLC
发明人： Holloway H. Frost , Rodolfo Vaghetto , Yassin A. Hassan , Lin Shao , Trevor D. Parker
IPC分类号： G21G1/08 , G21G1/10 , G21C3/54 , G21C5/12 , G21C3/58
摘要： A method of generating power using a Thorium-containing molten salt fuel is disclosed. One example includes the steps of providing a vessel containing a molten salt fuel, generating a proton beam externally to the vessel, where the externally generated proton beam is of an energy level sufficient to interact with material within a fuel rod in the vessel to produce (p, n) reactions resulting in the generation of neutrons at a first energy level. Neutrons generated within the vessel through the (p, n) reactions are utilized to produce a fission reaction which increases the heat content of the molten salt within the vessel. In the example, a heat exchanger is used to extract heat from the molten salt within the vessel and power is generated from the extracted heat.

2. 发明申请

US20220310281A1 TARGETRY COUPLED SEPARATIONS 有权
公开(公告)号：US20220310281A1
公开(公告)日：2022-09-29
申请号：US17533264
申请日：2021-11-23
申请人： TerraPower, LLC
发明人： Ken Czerwinski , Joshua C. Walter , Christopher P. Dunckley
IPC分类号： G21G1/02 , B01D11/04 , B01D15/40 , B01D11/02 , G21C19/42 , G21G1/08
摘要： Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

3. 发明授权

US10141079B2 Targetry coupled separations 有权
公开(公告)号：US10141079B2
公开(公告)日：2018-11-27
申请号：US14757683
申请日：2015-12-23
申请人： TerraPower, LLC
发明人： Ken Czerwinski , Joshua C. Walter
IPC分类号： G21G1/02 , B01D11/04 , B01D15/40 , B01D11/02 , G21C19/42 , G21G1/08 , G21G1/00
摘要： Targetry coupled separation refers to enhancing the production of a predetermined radiation product through the selection of a target (including selection of the target material and the material's physical structure) and separation chemistry in order to optimize the recovery of the predetermined radiation product. This disclosure describes systems and methods for creating (through irradiation) and removing one or more desired radioisotopes from a target and further describes systems and methods that allow the same target to undergo multiple irradiations and separation operations without damage to the target. In contrast with the prior art that requires complete dissolution or destruction of a target before recovery of any irradiation products, the repeated reuse of the same physical target allowed by targetry coupled separation represents a significant increase in efficiency and decrease in cost over the prior art.

4. 发明授权

US09734926B2 Device and method for producing medical isotopes 有权
公开(公告)号：US09734926B2
公开(公告)日：2017-08-15
申请号：US12990758
申请日：2009-05-01
申请人： Gregory Piefer
发明人： Gregory Piefer
IPC分类号： G21K5/08 , G21G1/08 , G21B1/01 , G21C1/30
CPC分类号： G21G1/08 , G21B1/01 , G21C1/303 , Y02E30/10 , Y02E30/40
摘要： A hybrid nuclear reactor for producing a medical isotope includes an ion source for producing an ion beam from a gas, a target chamber including a target that interacts with the ion beam to produce neutrons, and an activation cell positioned proximate the target chamber and including a parent material that interacts with the neutrons to produce the medical isotope via a fission reaction.

5. 发明申请

US20160187270A1 System For Active Long Range Detection And Identification Of Special Nuclear Materials Using A High Intensity Particle Beam 审中-公开
标题翻译：使用高强度粒子束主动长距离检测和识别特殊核材料的系统
公开(公告)号：US20160187270A1
公开(公告)日：2016-06-30
申请号：US15015346
申请日：2016-02-04
申请人： Brookhaven Science Associates, LLC
发明人： Istvan Dioszegi , Leon Forman , Peter E. Vanier , Cynthia A. Salwen
IPC分类号： G01N23/222 , G21G1/08
CPC分类号： G01N23/222 , G21G1/08
摘要： A long-range method and a system for reliably detecting and identifying special nuclear materials is provided that relies on the emission of delayed neutrons present in the decay of fission products (delayed neutron precursors) as a unique signature for the special nuclear materials, such as highly enriched uranium (235/238U). The method relies on a time-of-flight measurement in the first 1 μs after the inducing radiation pulse, and pulse height data analysis for both neutrons and gamma rays that can be done at a much higher data rate than in traditional pulse processing systems. The thermal neutron fission within the time regime of 100-500 μs provides a unique signature of special nuclear materials such as the highly enriched uranium.
摘要翻译：提供了一种远程方法和可靠地检测和识别特殊核材料的系统，其依赖于存在于裂变产物（延迟中子前体）衰变中的延迟中子的排放作为特殊核材料的独特签名，例如高浓铀（235 / 238U）。该方法依赖于在诱导辐射脉冲之后的前1μs内的飞行时间测量，以及可以以比传统脉冲处理系统高得多的数据速率进行的中子和伽马射线的脉冲高度数据分析。在100-500μs的时间范围内的热中子裂变提供了特殊核材料（如高浓缩铀）的独特签名。

6. 发明授权

US5355394A Method for producing actinium-225 and bismuth-213 失效
标题翻译：锕-225和铋-213的制备方法
公开(公告)号：US5355394A
公开(公告)日：1994-10-11
申请号：US916835
申请日：1992-08-10
申请人： Jacobus N. C. van Geel , Jean J. Fuger , Lothar Koch
发明人： Jacobus N. C. van Geel , Jean J. Fuger , Lothar Koch
IPC分类号： A61N5/00 , A61K51/12 , G21G1/06 , G21G1/08 , G21G4/08 , G21G1/02
CPC分类号： A61K51/1282 , G21G1/06
摘要： The invention relates to a method for producing actinium-225 and bismuth-213. According to the invention, radium-226 is irradiated in the thermal neutron flux of a nuclear reactor, the thorium fraction of the irradiation product is then chemically isolated and therefrom the actinium and radium mixture growing continuously by decay therein is chemically separated, this mixture serving as "cow" for the desired radionuclides which are growing continuously.
摘要翻译： PCT No.PCT / EP91 / 00306 Sec。 371日期：1992年8月10日 102（e）日期1992年8月10日PCT 1991年2月18日提交PCT公布。 WO91 / 13443 PCT出版物 1991年9月5日，本发明涉及锕-225和铋-213的制造方法。根据本发明，在核反应堆的热中子通量中照射镭-226，然后化学分离照射产物的钍馏分，由此通过其中的衰变连续生长的锕和镭混合物被化学分离，这种混合物作为连续生长的所需放射性核素的“牛”。

7. 发明授权

US2741665A Control of an automatic signalling system 失效
标题翻译：自动信令系统的控制
公开(公告)号：US2741665A
公开(公告)日：1956-04-10
申请号：US31996352
申请日：1952-11-12
申请人： NEDERLANDEN STAAT
发明人： MARIE OBERMAN ROELOF MAARTEN
IPC分类号： G21C1/00 , G21G1/08 , H04Q3/00
CPC分类号： H04Q3/0004 , G21C1/00 , G21G1/08 , Y02E30/30 , Y02E30/40

8. 发明申请

US20230041327A1 Methods of Energy Generation from a Thorium Molten Salt System 有权
公开(公告)号：US20230041327A1
公开(公告)日：2023-02-09
申请号：US17444483
申请日：2021-08-05
申请人： Texas Thorium LLC
发明人： Holloway H. Frost , Rodolfo Vaghetto , Yassin A. Hassan , Lin Shao , Trevor D. Parker
IPC分类号： G21G1/08 , G21G1/10 , G21C3/54
摘要： A method of generating power using a Thorium-containing molten salt fuel is disclosed. One example of the disclosed method includes the steps of providing a vessel containing a molten salt fuel, the molten salt fuel comprising Thorium and at least one salt containing a nucleus capable of interacting with a proton of sufficient energy to produce a (p, n) reaction resulting in the generation of a neutron at a first energy level and generating a proton beam externally to the vessel, where the externally generated proton beam being of an energy level sufficient to interact with the at least one salt in the vessel to produce a (p, n) reaction resulting in the generation of a neutron at the first energy level. In the example, the externally generated proton beam is directed into the vessel such that at least some protons forming the beam will interact with an atom forming a part of the at least one salt contained in the vessel to causing interaction between the externally generated proton beam and the at least one salt contained in the vessel to produce (p, n) reactions resulting in the generation of neutrons within the vessel and an absorption reaction involving the generated neutrons and Thorium within the vessel. Neutrons generated within the vessel through the (p, n) reactions caused by the externally generated proton’s interaction with the at least one salt are utilized to produce a fission reaction where the fission reaction increases. the heat content of the molten salt within the vessel. In the example, a heat exchanger is used to extract heat from the molten salt within the vessel and power is generated from the extracted heat.

9. 发明申请

US20220301736A1 AQUEOUS ASSEMBLY AND CONTROL METHOD 有权
公开(公告)号：US20220301736A1
公开(公告)日：2022-09-22
申请号：US17745637
申请日：2022-05-16
申请人： SHINE Technologies, LLC
发明人： Gregory Piefer , Eric N. Van Abel
IPC分类号： G21G1/00 , G21G1/08 , G21C3/42 , G21C1/26 , G21C7/34 , G21C1/30 , G21C7/02
摘要： An aqueous assembly has a negative coefficient of reactivity with a magnitude. The aqueous assembly includes a vessel and an aqueous solution, with a fissile solute, supported in the vessel. A reactivity stabilizer is disposed within the aqueous solution to reduce the magnitude of the negative coefficient of reactivity of the aqueous assembly during operation of the aqueous assembly.

10. 发明授权

US11361873B2 Aqueous assembly and control method 有权
公开(公告)号：US11361873B2
公开(公告)日：2022-06-14
申请号：US14390658
申请日：2013-03-15
申请人： SHINE MEDICAL TECHNOLOGIES, INC.
发明人： Gregory Piefer , Eric N. Van Abel
IPC分类号： G21C1/30 , G21G1/00 , G21G1/08 , G21C3/42 , G21C1/26 , G21C7/34 , G21C7/02 , G21C1/24
摘要： An aqueous assembly has a negative coefficient of reactivity with a magnitude. The aqueous assembly includes a vessel and an aqueous solution, with a fissile solute, supported in the vessel. A reactivity stabilizer is disposed within the aqueous solution to reduce the magnitude of the negative coefficient of reactivity of the aqueous assembly during operation of the aqueous assembly.

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