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公开(公告)号：US10395787B2
公开(公告)日：2019-08-27
申请号：US15759509
申请日：2016-12-14
Applicant: CLEAR INC.
Inventor： Osao Sumita , Isao Ueno , Takehiko Yokomine
Abstract: Provided is a nuclear reactor system and method therefor, for increasing the speed of conversion of a radionuclide to a stable nuclide to reduce radionuclide concentration using thermal neutrons produced by reducing the velocity of fast neutrons, while simultaneously subjecting fast-neutron-induced thermal energy of a primary cooling material to heat exchange with a secondary cooling material in a heat exchanger (7), and feeding the energy to a turbine system to generate power, the system having a nuclear reactor container (1) comprising a first container (11), and a second container (12), a plurality of metal fuel assemblies (22) and a liquid metal, which is the primary cooling material, being disposed in the first container, and the second cooling material capable of dual use as a neutron moderator and a MA radioactivity-extinguishing assembly or FP-extinguishing assembly (24) being loaded in the second container.
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公开(公告)号：US20190311816A1
公开(公告)日：2019-10-10
申请号：US16096228
申请日：2017-04-25
Applicant: Clear Inc.
Inventor： Osao SUMITA , Isao UENO , Takehiko YOKOMINE
Abstract: Engineering safety systems always have insufficiencies in terms of safety, and construction of a complete safety system causes installation costs for the safety system to become very high. Provided is a small nuclear reactor HAVING a load following control system in which a nuclear reaction in the nuclear reactor is naturally controlled by the generated heat, the small nuclear reactor being provided with: a reactor core provided with a plurality of fuel assemblies of metallic fuels containing uranium (U) 235, 238 and/or plutonium (Pu) 239; a primary coolant comprising a liquid metal; a neutron reflector which serves to control the nuclear reaction in the reactor core and is disposed to enclose the periphery of the reactor core; and a mechanism which contains a liquid or a gas having an expansion coefficient greater than that of the neutron reflector, converts the coefficient of volumetric expansion into an amount of linear thermal expansion, and, by using same, moves the neutron reflector or adjusts the spacing between the plurality of fuel assemblies.
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公开(公告)号：US10522259B2
公开(公告)日：2019-12-31
申请号：US15329646
申请日：2016-01-25
Applicant: CLEAR INC.
Inventor： Osao Sumita , Isao Ueno , Takehiko Yokomine
IPC: G21C7/10 , G21D3/12 , G21C1/02 , G21C7/02 , G21C7/28 , G21C1/06 , G21C11/06 , G21D3/16 , G21C7/00 , G21D3/08
Abstract: A nuclear power generation system being safe and easily controlled by load following. The nuclear power generation system has a nuclear reactor employing a load following control method. The reactor includes: a fuel assembly reactor core having metallic fuel containing at least one selected from uranium-235, uranium-238 and plutonium-239; a reactor vessel containing the reactor core; metallic sodium loaded into the reactor vessel and heated by the reactor core; and a neutron reflector for achieving criticality in the reactor core with effective multiplication factor of neutrons emitted from the reactor core being maintained at or above about 1. The neutron reflector is coupled to spring or spiral metallic members and utilizing heat deformation in the metallic members due to the temperature in coolant metallic sodium to control the fast neutron reflection efficiency of the neutron reflector.
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公开(公告)号：US09801396B2
公开(公告)日：2017-10-31
申请号：US14774326
申请日：2014-03-07
Applicant: TECH CORPORATION CO., LTD. , CLEAR INC.
Inventor： Choonok Park
IPC: A23F5/26 , C02F1/44 , C02F1/467 , A23F3/18 , B01D61/42 , C02F1/20 , C02F1/68 , C02F1/28 , C02F1/42
CPC classification number: A23F5/26 , A23F3/18 , B01D61/422 , C02F1/20 , C02F1/281 , C02F1/42 , C02F1/441 , C02F1/4676 , C02F1/68 , C02F2201/46115
Abstract: [Problem] To provide a production method for a natural-extract beverage which is coffee extraction or the like using electrolytically reduced water, wherein the oxidation-reduction potential of the extract is negative.[Solution] A method for producing a natural-extract beverage by making coffee or tea with electrolytically reduced hot water containing dissolved hydrogen molecules, comprising making coffee or tea that an oxidation-reduction potential of the extract is made to be 0 mV or less by at least one means that suppresses volatilization of dissolved molecular hydrogen, wherein the at least one means are selected from the group consisting of: means of using electrolytically reduced water obtained by electrolysis of heated source water, means of performing the extraction under high pressure in a sealed container, and means of adding to the electrolytically reduced water at least one dissolved-hydrogen stabilizing agent selected from polysaccharides and/or polyphenols.
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Patent Agency Ranking
公开(公告)号：US10400343B2
公开(公告)日：2019-09-03
申请号：US15740994
申请日：2016-09-20
Applicant: CLEAR INC.
Inventor： Osao Sumita , Isao Ueno , Takehiko Yokomine
Abstract: A molten salt electrolysis tank, comprises: an anode feeder which is equipped with a mechanism for recovering deteriorated contact resistance that takes place between the metal fuel rod and the anode in the course of the anodic electrolysis; a cathode feeder which is controlled so as to have a potential in a range that causes U and/or Pu ions to be reduced to metal; a heating mechanism for locally heating the metal fuel rod and/or an excitation mechanism for bringing the metal fuel rod into a locally excited state; and a solenoid coil or a permanent magnet that is disposed between the anode feeder and the cathode feeder so as to improve separation efficiency of U and/or Pu ions by applying a combination of an electric field and a magnetic field.
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公开(公告)号：US20190115116A1
公开(公告)日：2019-04-18
申请号：US15759509
申请日：2016-12-14
Applicant: CLEAR INC.
Inventor： Osao SUMITA , Isao UENO , Takehiko YOKOMINE
CPC classification number: G21D1/006 , G21C1/024 , G21C1/28 , G21C3/32 , G21C11/06 , G21C15/28 , G21D1/00 , G21F9/28 , G21G1/02 , Y02E30/34
Abstract: Provided is a nuclear reactor system and method therefor, for increasing the speed of conversion of a radionuclide to a stable nuclide to reduce radionuclide concentration using thermal neutrons produced by reducing the velocity of fast neutrons, while simultaneously subjecting fast-neutron-induced thermal energy of a primary cooling material to heat exchange with a secondary cooling material in a heat exchanger (7), and feeding the energy to a turbine system to generate power, the system having a nuclear reactor container (1) comprising a first container (11), and a second container (12), a plurality of metal fuel assemblies (22) and a liquid metal, which is the primary cooling material, being disposed in the first container, and the second cooling material capable of dual use as a neutron moderator and a MA radioactivity-extinguishing assembly or FP-extinguishing assembly (24) being loaded in the second container.
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公开(公告)号：US20170213610A1
公开(公告)日：2017-07-27
申请号：US15329646
申请日：2016-01-25
Applicant: CLEAR INC.
Inventor： Osao SUMITA , Isao UENO , Takehiko YOKOMINE
Abstract: The present invention provides a small nuclear power generation system being safe and easily controlled by load following, and allowing reductions in manufacturing costs and maintenance and management costs. The small nuclear power generation system has a small nuclear reactor employing a load following control method. The reactor includes: a fuel assembly reactor core 4 having metallic fuel containing one or both of uranium (235, 238) and plutonium-239; a reactor vessel 1 containing the fuel assembly reactor core 4; metallic sodium loaded into the reactor vessel 1 and heated by the fuel assembly reactor core 4; and a neutron reflector 2 for achieving criticality in the reactor core with effective multiplication factor of neutrons emitted from the fuel assembly reactor core 4 being maintained at or above about 1. The load following control method of the reactor allows a neutron effective multiplication factor to be controlled by coupling the neutron reflector to spring or spiral metallic members and utilizing heat deformation in the metallic members due to the temperature in coolant metallic sodium to control the fast neutron reflection efficiency of the neutron reflector
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公开(公告)号：US10991468B2
公开(公告)日：2021-04-27
申请号：US16096228
申请日：2017-04-25
Applicant: Clear Inc.
Inventor： Osao Sumita , Isao Ueno , Takehiko Yokomine
IPC: G21C7/28 , G21C1/02 , G21C3/02 , G21C7/02 , G21C7/30 , G21C11/06 , G21C7/10 , G21D3/16 , G21D3/12
Abstract: Provided is a nuclear reactor having a load following control system in which a nuclear reaction therein is naturally controlled by the generated heat, the nuclear reactor being provided with: a reactor core provided with a plurality of fuel assemblies of metallic fuels containing uranium (U) 235, 238 and/or plutonium (Pu) 239; a primary coolant comprising a liquid metal; a neutron reflector which serves to control the nuclear reaction in the reactor core and is disposed to enclose the periphery of the reactor core; and a mechanism which contains a-liquid or a gas having a thermal expansion coefficient greater than that of the neutron reflector, and converts the coefficient of volumetric expansion into an amount of linear thermal expansion, and, by using same, moves the neutron reflector or adjusts the spacing between the plurality of fuel assemblies.
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公开(公告)号：US20180202057A1
公开(公告)日：2018-07-19
申请号：US15740994
申请日：2016-09-20
Applicant: CLEAR INC.
Inventor： Osao SUMITA , Isao UENO , Takehiko YOKOMINE
Abstract: A molten salt electrolysis tank, comprises: an anode feeder which is equipped with a mechanism for recovering deteriorated contact resistance that takes place between the metal fuel rod and the anode in the course of the anodic electrolysis; a cathode feeder which is controlled so as to have a potential in a range that causes U and/or Pu ions to be reduced to metal; a heating mechanism for locally heating the metal fuel rod and/or an excitation mechanism for bringing the metal fuel rod into a locally excited state; and a solenoid coil or a permanent magnet that is disposed between the anode feeder and the cathode feeder so as to improve separation efficiency of U and/or Pu ions by applying a combination of an electric field and a magnetic field.
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