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1.发明申请公开(公告)号：US20160189813A1
公开(公告)日：2016-06-30
申请号：US14981512
申请日：2015-12-28
申请人： TerraPower, LLC
发明人： Anselmo T. Cisneros, JR. , Ken Czerwinski , Bassem S. El-Dasher , William M. Kerlin , Kevin Kramer , Jeffery F. Latkowski , Robert C. Petroski , Joshua C. Walter
IPC分类号： G21C19/303 , G21C15/28 , G21C19/50 , G21C1/22
摘要： This disclosure describes nuclear fuel salts usable in certain molten salt reactor designs and related systems and methods. Binary, ternary and quaternary chloride fuel salts of uranium, as well as other fissionable elements, are described. In addition, fuel salts of UClxFy are disclosed as well as bromide fuel salts. This disclosure also presents methods and systems for manufacturing such fuel salts, for creating salts that reduce corrosion of the reactor components and for creating fuel salts that are not suitable for weapons applications.
摘要翻译： 本公开描述了可用于某些熔盐反应器设计和相关系统和方法的核燃料盐。 描述了铀的二元，三元和四元氯化物燃料盐以及其它可裂变元素。 此外，还公开了UClxFy的燃料盐以及溴化物燃料盐。 本公开还提供了用于制造这种燃料盐的方法和系统，用于产生减少反应器部件的腐蚀并产生不适用于武器应用的燃料盐的盐。
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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
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.
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公开(公告)号：US20200251231A1
公开(公告)日：2020-08-06
申请号：US16782652
申请日：2020-02-05
申请人： TerraPower, LLC
摘要： This disclosure describes systems and methods for synthesizing UCl3 from UCl4. These systems and methods may also be used to directly synthesize binary and ternary embodiments of uranium salts of chloride usable as nuclear fuel in certain molten salt reactor designs. The systems and methods described herein are capable of synthesizing any desired uranium chloride fuel salt that is a combination of UCl4, UCl3 and one or more non-fissile chloride compounds, such as NaCl. In particular, the systems and methods described herein are capable of synthesizing any UCl3—UCl4—NaCl or UCl3—NaCl fuel salt composition from UCl4—NaCl.
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公开(公告)号：US20200211724A1
公开(公告)日：2020-07-02
申请号：US16676183
申请日：2019-11-06
申请人： TerraPower, LLC
发明人： Anselmo T. Cisneros, JR. , Ken Czerwinski , Bassem S. El-Dasher , Brian C. Kelleher , William M. Kerlin , Kevin Kramer , Jeffery F. Latkowski , Robert C. Petroski , Joshua C. Walter
摘要： An anti-proliferation technique is disclosed to reduce the likelihood of nuclear proliferation due to the use fissionable fuel salts. The technique includes doping the fuel salt with one or more elements (referred to herein as activation dopants) that, upon exposure to neutrons such as would occur in the fuel salt when a reactor is in operation, undergo a nuclear reaction to, directly or indirectly, form highly active “protecting isotopes” (of the same element as the activation dopant or a different element). A sufficient mass of activation dopants is used so that the Figure of Merit (FOM) of the fuel salt is decreased to below 1.0 within some target number of days of fission. This allows the FOM of the fuel salt to be controlled so that the fuel becomes too dangerous to handle before to the creation of a significant amount of weaponizable isotopes.
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公开(公告)号：US10566096B2
公开(公告)日：2020-02-18
申请号：US15673188
申请日：2017-08-09
申请人： TerraPower, LLC
摘要： This disclosure describes systems and methods for synthesizing UCl3 from UCl4. These systems and methods may also be used to directly synthesize binary and ternary embodiments of uranium salts of chloride usable as nuclear fuel in certain molten salt reactor designs. The systems and methods described herein are capable of synthesizing any desired uranium chloride fuel salt that is a combination of UCl4, UCl3 and one or more non-fissile chloride compounds, such as NaCl. In particular, the systems and methods described herein are capable of synthesizing any UCl3—UCl4—NaCl or UCl3—NaCl fuel salt composition from UCl4—NaCl.
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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
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.
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公开(公告)号：US20220363557A1
公开(公告)日：2022-11-17
申请号：US17742116
申请日：2022-05-11
申请人： TerraPower, LLc
发明人： Ken Czerwinski , Hilary Fitzgerald
IPC分类号： C01F17/00
摘要： The actinium generator described herein is based on peroxide precipitation of thorium from its daughter products radium and actinium. In this system, the “actinium generator” is a quantity of solid thorium peroxide stored under a cover solution. The thorium peroxide is stored as a suspension to allow for the buildup of the decay products radium and actinium in the suspension. The suspension is then treated with a peroxide solution and the solid and liquid phases are separated. The thorium remains in the solid peroxide form while the soluble actinium and radium are removed with the liquid phase in a rinsing step. After rinsing, an amount of the rinsing solution is retained with the thorium peroxide solid as a fresh cover solution to form another suspension for storage. This new suspension is then stored to allow actinium and radium to again build up in the suspension for a subsequent separation cycle.
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公开(公告)号：US20190139665A1
公开(公告)日：2019-05-09
申请号：US16174364
申请日：2018-10-30
申请人： TerraPower, LLC
发明人： Ken Czerwinski , Joshua C. Walter
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.
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公开(公告)号：US20170301413A1
公开(公告)日：2017-10-19
申请号：US15584926
申请日：2017-05-02
申请人： TerraPower, LLC
发明人： Anselmo T. Cisneros, JR. , Ken Czerwinski , Bassem S. El-Dasher , Brian C. Kelleher , William M. Kerlin , Kevin Kramer , Jeffery F. Latkowski , Robert C. Petroski , Joshua C. Walter
CPC分类号： G21C1/03 , G21C1/22 , G21C3/22 , G21C3/54 , G21C7/30 , G21C15/28 , G21C19/28 , G21C19/303 , G21C19/307 , G21C19/50 , Y02E30/34 , Y02E30/35 , Y02E30/38 , Y02E30/39
摘要： This disclosure describes nuclear fuel salts usable in certain molten salt reactor designs and related systems and methods. Binary, ternary and quaternary chloride fuel salts of uranium, as well as other fissionable elements, are described. In addition, fuel salts of UClxFy are disclosed as well as bromide fuel salts. This disclosure also presents methods and systems for manufacturing such fuel salts, for creating salts that reduce corrosion of the reactor components and for creating fuel salts that are not suitable for weapons applications.
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公开(公告)号：US20160189812A1
公开(公告)日：2016-06-30
申请号：US14980617
申请日：2015-12-28
申请人： TerraPower, LLC
发明人： Ken Czerwinski , Joshua C. Walter
摘要： This disclosure describes systems and methods for treating nuclear fuel with supercritical fluids, such as supercritical carbon dioxide. The addition of various ligands to the supercritical fluids is disclosed, where one or more ligands can be chosen to selectively remove one or more fission products from the nuclear fuel. The nuclear fuel may be treated either within the nuclear reactor or may be removed from the reactor before treatment. This disclosure also presents methods and systems for liquid nuclear fuel treatment with supercritical fluids in, for example, a molten salt fast reactor, a traveling wave reactor, and a containerized molten salt reactor.
摘要翻译： 本公开描述了用超临界流体如超临界二氧化碳处理核燃料的系统和方法。 公开了向超临界流体添加各种配体，其中可以选择一种或多种配体以选择性地从核燃料中除去一种或多种裂变产物。 核燃料可以在核反应堆内处理，也可以在处理前从反应器中除去。 本公开还提出了在例如熔盐快堆，行波反应器和容器化熔盐反应器中用超临界流体进行液体核燃料处理的方法和系统。
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