Patents by Inventor Jeffery F. Latkowski
Jeffery F. Latkowski has filed for patents to protect the following inventions. This listing includes patent applications that are pending as well as patents that have already been granted by the United States Patent and Trademark Office (USPTO).
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Patent number: 11798694Abstract: A molten fuel salt nuclear reactor core assembly including a fluid neutron reflecting material defining a fast spectrum fuel volume configured to breed fissile fuel from fertile fuel, a first inlet channel, and a first outlet channel through which cooled molten fuel salt can enter and heated molten fuel salt can exit the fast spectrum fuel volume. The core assembly also includes a set of neutron absorbing members sized to fit within the fast spectrum fuel volume. The set of neutron absorbing members define a thermal spectrum fuel volume for a fission reaction of the fissile fuel, a second inlet channel, and a second outlet channel through which cooled molten fuel salt can enter and heated molten fuel salt can exit the thermal spectrum fuel volume.Type: GrantFiled: October 21, 2020Date of Patent: October 24, 2023Assignee: TerraPower, LLCInventors: Anselmo T. Cisneros, Jr., Charles Gregory Freeman, Kevin Kramer, Jeffery F. Latkowski
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Patent number: 11791057Abstract: A reflector assembly for a molten chloride fast reactor (MCFR) includes a support structure with a substantially cylindrical base plate, a substantially cylindrical top plate, and a plurality of circumferentially spaced ribs extending between the base plate and the top plate. The support structure is configured to encapsulate a reactor core for containing nuclear fuel. The MCFR also includes a plurality of tube members disposed within the support structure and extending axially between the top plate and the bottom plate. The plurality of tube members are configured to hold at least one reflector material to reflect fission born neutrons back to a center of the reactor core.Type: GrantFiled: July 6, 2021Date of Patent: October 17, 2023Assignee: TerraPower, LLCInventors: Anselmo T. Cisneros, Jr., Charles Gregory Freeman, Kevin Kramer, Jeffery F. Latkowski
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Patent number: 11488731Abstract: This disclosure describes various configurations and components of a molten fuel fast or thermal nuclear reactor for managing the operating temperature in the reactor core. The disclosure includes various configurations of direct reactor auxiliary cooling system (DRACS) heat exchangers and primary heat exchangers as well as descriptions of improved flow paths for nuclear fuel, primary coolant and DRACS coolant through the reactor components.Type: GrantFiled: October 26, 2020Date of Patent: November 1, 2022Assignee: TerraPower, LLCInventors: Ryan Abbott, Anselmo T. Cisneros, Jr., Daniel Flowers, Charles Gregory Freeman, Mark A. Havstad, Kevin Kramer, Jeffery F. Latkowski, Jon D. McWhirter, John R. Suyes, III
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Publication number: 20220301729Abstract: Configurations of molten fuel salt reactors are described that allow for active cooling of the containment vessel of the reactor by the primary coolant. Furthermore, naturally circulating reactor configurations are described in which the reactor cores are substantially frustum-shaped so that the thermal center of the reactor core is below the outlet of the primary heat exchangers. Heat exchanger configurations are described in which welded components are distanced from the reactor core to reduce the damage caused by neutron flux from the reactor. Radial loop reactor configurations are also described.Type: ApplicationFiled: May 12, 2022Publication date: September 22, 2022Inventors: Anselmo T. Cisneros, JR., Christopher J. Johns, Brian C. Kelleher, Kevin Kramer, Jeffery F. Latkowski, Jon D. McWhirter
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Patent number: 11387007Abstract: An architecture for an inertial confinement fusion system is disclosed. The system includes a fusion chamber for producing neutrons from a fusion reaction, and a laser system in which lasers are arranged about a vacuum chamber to provide energy to the fusion chamber to initiate the fusion reaction. The beam paths between the lasers and the fusion chamber are configured to prevent neutrons from the fusion chamber from reaching the laser system at a level that would preclude human access to the laser system.Type: GrantFiled: November 8, 2011Date of Patent: July 12, 2022Assignee: Lawrence Livermore National Security, LLCInventors: Edward I. Moses, Jeffery F. Latkowski, Thomas M. Anklam, Mary L. Spaeth, Anthony Michael Dunne, Richard H. Sawicki, Robert J. Deri, Robin R. Miles, Andrew J. Bayramian, Kenneth R. Manes, Peter A. Amendt, Alvin C. Erlandson
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Patent number: 11367536Abstract: Configurations of molten fuel salt reactors are described that allow for active cooling of the containment vessel of the reactor by the primary coolant. Furthermore, naturally circulating reactor configurations are described in which the reactor cores are substantially frustum-shaped so that the thermal center of the reactor core is below the outlet of the primary heat exchangers. Heat exchanger configurations are described in which welded components are distanced from the reactor core to reduce the damage caused by neutron flux from the reactor. Radial loop reactor configurations are also described.Type: GrantFiled: March 19, 2020Date of Patent: June 21, 2022Assignee: TerraPower, LLCInventors: Ryan Abbott, Anselmo T. Cisneros, Jr., Daniel Flowers, Charles Gregory Freeman, Mark A. Havstad, Christopher J. Johns, Brian C. Kelleher, Kevin Kramer, Jeffery F. Latkowski, Jon D. McWhirter
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Publication number: 20220139577Abstract: 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.Type: ApplicationFiled: January 20, 2022Publication date: May 5, 2022Inventors: 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
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Patent number: 11276503Abstract: 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.Type: GrantFiled: November 6, 2019Date of Patent: March 15, 2022Assignee: TerraPower, LLCInventors: 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
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Patent number: 11170901Abstract: A molten salt reactor includes a nuclear reactor core for sustaining a nuclear fission reaction fueled by a molten fuel salt. A molten fuel salt control system removes a volume of the molten fuel salt from the nuclear reactor core to maintain a reactivity parameter within a range of nominal reactivity. The molten fuel salt control system includes a molten fuel salt exchange system that fluidically couples to the nuclear reactor core and exchanges a volume of the molten fuel salt with a volume of a feed material containing a mixture of a selected fertile material and a carrier salt. The molten fuel salt control system can include a volumetric displacement control system having one or more volumetric displacement bodies insertable into the nuclear reactor core. Each volumetric displacement body can remove a volume of molten fuel salt from the nuclear reactor core, such as via a spill-over system.Type: GrantFiled: October 7, 2019Date of Patent: November 9, 2021Assignee: TerraPower, LLCInventors: Jesse R. Cheatham, III, Anselmo T. Cisneros, Jr., Jeffery F. Latkowski, James M. Vollmer, Christopher J. Johns
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Publication number: 20210343431Abstract: A reflector assembly for a molten chloride fast reactor (MCFR) includes a support structure with a substantially cylindrical base plate, a substantially cylindrical top plate, and a plurality of circumferentially spaced ribs extending between the base plate and the top plate. The support structure is configured to encapsulate a reactor core for containing nuclear fuel. The MCFR also includes a plurality of tube members disposed within the support structure and extending axially between the top plate and the bottom plate. The plurality of tube members are configured to hold at least one reflector material to reflect fission born neutrons back to a center of the reactor core.Type: ApplicationFiled: July 6, 2021Publication date: November 4, 2021Inventors: Anselmo T. Cisneros, JR., Charles Gregory Freeman, Kevin Kramer, Jeffery F. Latkowski
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Publication number: 20210272708Abstract: Designs for a low power, fast spectrum molten fuel nuclear reactor that can be used to advance the understanding of molten salt reactors, their design and their operation are described. Furthermore, the designs described may be adapted to extra-terrestrial use as described herein for use as a low-gravity, moon-, Mars-, or space-based power generator. These low power reactors include a reactor core volume defined by a radial neutron reflector enclosed in a reactor vessel, in which heated fuel salt flows from the reactor core through a duct between the radial neutron reflector and the reactor vessel and back into the reactor core. Heat generated from the fission in the reactor core is transferred from the molten fuel through the reactor vessel to a coolant, in the case of an experimental design, or directly to an extra-terrestrial environment, in the case of an extra-terrestrial design.Type: ApplicationFiled: December 23, 2020Publication date: September 2, 2021Inventors: Anselmo T. Cisneros, JR., Charles Gregory Freeman, Samuel S. Goodrich, Kevin Kramer, Jeffery F. Latkowski, Gregory T. Markham, Jon D. McWhirter, James A. Roecker, Justin W. Thomas, Daniel J. Walter, Kent E. Wardle
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Patent number: 11075015Abstract: A reflector assembly for a molten chloride fast reactor (MCFR) includes a support structure with a substantially cylindrical base plate, a substantially cylindrical top plate, and a plurality of circumferentially spaced ribs extending between the base plate and the top plate. The support structure is configured to encapsulate a reactor core for containing nuclear fuel. The MCFR also includes a plurality of tube members disposed within the support structure and extending axially between the top plate and the bottom plate. The plurality of tube members are configured to hold at least one reflector material to reflect fission born neutrons back to a center of the reactor core.Type: GrantFiled: March 12, 2019Date of Patent: July 27, 2021Assignee: TerraPower, LLCInventors: Anselmo T. Cisneros, Jr., Charles Gregory Freeman, Kevin Kramer, Jeffery F. Latkowski
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Publication number: 20210210222Abstract: This disclosure describes various configurations and components of a molten fuel fast or thermal nuclear reactor for managing the operating temperature in the reactor core. The disclosure includes various configurations of direct reactor auxiliary cooling system (DRACS) heat exchangers and primary heat exchangers as well as descriptions of improved flow paths for nuclear fuel, primary coolant and DRACS coolant through the reactor components.Type: ApplicationFiled: October 26, 2020Publication date: July 8, 2021Inventors: Ryan Abbott, Anselmo T. Cisneros, JR., Daniel Flowers, Charles Gregory Freeman, Mark A. Havstad, Kevin Kramer, Jeffery F. Latkowski, Jon D. McWhirter, John R. Suyes, III
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Publication number: 20210210224Abstract: Configurations of molten fuel salt reactors are described that utilize neutron-reflecting coolants or a combination of primary salt coolants and secondary neutron-reflecting coolants. Further configurations are described that circulate liquid neutron-reflecting material around a reactor core to control the neutronics of the reactor. Furthermore, configurations which use the circulating neutron-reflecting material to actively cool the containment vessel are also described. A further configuration is described that utilizes a core barrel between a reactor core volume of molten fuel salt and a reflector volume, in which the reflector volume contains a plurality of individual reflector elements separated by an interstitial space filled with molten fuel salt.Type: ApplicationFiled: October 21, 2020Publication date: July 8, 2021Inventors: Anselmo T. Cisneros, JR., Charles Gregory Freeman, Kevin Kramer, Jeffery F. Latkowski
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Patent number: 10923238Abstract: This disclosure describes various configurations and components of a molten fuel fast or thermal nuclear reactor for managing the operating temperature in the reactor core. The disclosure includes various configurations of direct reactor auxiliary cooling system (DRACS) heat exchangers and primary heat exchangers as well as descriptions of improved flow paths for nuclear fuel, primary coolant and DRACS coolant through the reactor components.Type: GrantFiled: November 15, 2017Date of Patent: February 16, 2021Assignee: TerraPower, LLCInventors: Ryan Abbott, Anselmo T. Cisneros, Jr., Daniel Flowers, Charles Gregory Freeman, Mark A. Havstad, Kevin Kramer, Jeffery F. Latkowski, Jon D. McWhirter, John R. Suyes, III
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Patent number: 10867710Abstract: Configurations of molten fuel salt reactors are described that utilize neutron-reflecting coolants or a combination of primary salt coolants and secondary neutron-reflecting coolants. Further configurations are described that circulate liquid neutron-reflecting material around a reactor core to control the neutronics of the reactor. Furthermore, configurations which use the circulating neutron-reflecting material to actively cool the containment vessel are also described. A further configuration is described that utilizes a core barrel between a reactor core volume of molten fuel salt and a reflector volume, in which the reflector volume contains a plurality of individual reflector elements separated by an interstitial space filled with molten fuel salt.Type: GrantFiled: October 13, 2017Date of Patent: December 15, 2020Assignee: TerraPower, LLCInventors: Anselmo T. Cisneros, Jr., Charles Gregory Freeman, Kevin Kramer, Jeffery F. Latkowski
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Publication number: 20200279660Abstract: Configurations of molten fuel salt reactors are described that allow for active cooling of the containment vessel of the reactor by the primary coolant. Furthermore, naturally circulating reactor configurations are described in which the reactor cores are substantially frustum-shaped so that the thermal center of the reactor core is below the outlet of the primary heat exchangers. Heat exchanger configurations are described in which welded components are distanced from the reactor core to reduce the damage caused by neutron flux from the reactor. Radial loop reactor configurations are also described.Type: ApplicationFiled: March 19, 2020Publication date: September 3, 2020Applicant: TerraPower, LLCInventors: Ryan Abbott, Anselmo T. Cisneros, JR., Daniel Flowers, Charles Gregory Freeman, Mark A. Havstad, Christopher J. Johns, Brian C. Kelleher, Kevin Kramer, Jeffery F. Latkowski, Jon D. McWhirter
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Patent number: 10741293Abstract: Configurations of molten fuel salt reactors are described that include an auxiliary cooling system which shared part of the primary coolant loop but allows for passive cooling of decay heat from the reactor. Furthermore, different pump configurations for circulating molten fuel through the reactor core and one or more in vessel heat exchangers are described.Type: GrantFiled: May 2, 2017Date of Patent: August 11, 2020Assignee: TerraPower, LLCInventors: Ryan Abbott, Anselmo T. Cisneros, Jr., Robert A. Corbin, Daniel Flowers, Charles Gregory Freeman, Mark A. Havstad, Christopher J. Johns, Brian C. Kelleher, Kevin Kramer, Jeffery F. Latkowski, Jon D. McWhirter
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Patent number: 10734122Abstract: A dynamic neutron reflector assembly for a “breed-and-burn” fast reactor incrementally adjusts neutron spectrum and reactivity in a reactor core. The composition of materials in the dynamic neutron reflector may be adjusted to change neutron reflectivity levels, or to introduce neutron moderating or absorption characteristics. The dynamic neutron reflector may contain a flowing reflecting liquid of adjustable volume and/or density. Submergible members may be selectively inserted into the flowing reflecting liquid to alter its volume and introduce other neutron modifying effects such as moderation or absorption. Selective insertion of the submergible members allows for concentration of the neutron modifying effects in a selected portion of the reactor core. The flowing reflecting liquid may also act as a secondary coolant circuit by exchanging heat with the molten fuel salt.Type: GrantFiled: September 30, 2016Date of Patent: August 4, 2020Assignee: TerraPower, LLCInventors: Anselmo T. Cisneros, Jr., Charles Gregory Freeman, Christopher J. Johns, Kevin Kramer, Jeffery F. Latkowski
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Publication number: 20200211724Abstract: 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.Type: ApplicationFiled: November 6, 2019Publication date: July 2, 2020Applicant: TerraPower, LLCInventors: 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