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公开(公告)号:US12176117B2
公开(公告)日:2024-12-24
申请号:US17023230
申请日:2020-09-16
Applicant: TerraPower, LLC
Inventor: Jesse R. Cheatham, III , Robert A. Corbin , John R. Gilleland , Pavel Hejzlar , Kevin Kramer , Christopher A. Martin , Brian Morris , Robert C. Petroski , Philip M. Schloss , Joshua C. Walter , Mark R. Werner
Abstract: An integrated energy system includes a nuclear thermal plant situated on a nuclear site. The nuclear thermal plant produces thermal energy that is transported to a thermal energy storage system located outside the nuclear site. The thermal storage system is thermally coupled to a power generation system which is also remote to the nuclear site. By this arrangement, the nuclear thermal plant is isolated and decoupled from the power generation system. The nuclear thermal plant may supply thermal energy upwards of 800° C. or more to be stored at the thermal energy storage system until needed such as for industrial heat, power generation, or other uses. The thermal storage system is source agnostic, and one or more additional thermal energy generators, such as additional nuclear reactors, solar thermal plants, or other thermal energy generators can be coupled to a common thermal storage system and power generation system.
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公开(公告)号:US20230111998A1
公开(公告)日:2023-04-13
申请号:US17950830
申请日:2022-09-22
Applicant: Terrestrial Energy Inc.
Inventor: David LEBLANC
Abstract: The present relates to the integration of the primary functional elements of graphite moderator and reactor vessel and/or primary heat exchangers and/or control rods into an integral molten salt nuclear reactor (IMSR). Once the design life of the IMSR is reached, for example, in the range of 3 to 10 years, it is disconnected, removed and replaced as a unit. The spent IMSR functions as the medium or long term storage of the radioactive graphite and/or heat exchangers and/or control rods and/or fuel salt contained in the vessel of the IMSR. The present also relates to a nuclear reactor that has a buffer salt surrounding the nuclear vessel. During normal operation of the nuclear reactor, the nuclear reactor operates at a temperature that is lower than the melting point of the buffer salt and the buffer salt acts as a thermal insulator. Upon loss of external cooling, the temperature of the nuclear reactor increases and melts the buffer salt, which can then transfer heat from the nuclear core to a cooled containment vessel.
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公开(公告)号:US20230075832A1
公开(公告)日:2023-03-09
申请号:US17759332
申请日:2021-01-21
Applicant: Battelle Energy Alliance, LLC
Inventor: Yasir Arafat , Douglas C. Crawford , Timothy A. Hyde , Jess C. Gehin , James W. Sterbentz , Robert C. O'Brien
Abstract: An energy production device may include a core and a heat exchanger positioned over the core. The core may include one or more fuel rods. The core may further include a heat transmission fluid configured to flow through natural convection upwards through the one or more fuel rods and collect heat therefrom. The core may also include a reaction control device including a neutron-absorbing material. The heat exchanger may be configured to receive the heat transmission fluid and transfer the heat to an energy harnessing device positioned on an opposite side of the heat exchanger from the core.
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公开(公告)号:US20220084697A1
公开(公告)日:2022-03-17
申请号:US17407529
申请日:2021-08-20
Applicant: TERRESTRIAL ENERGY USA, INC.
Inventor: John H. KUTSCH , Anthonius Cornelis RODENBURG
Abstract: The power plant system includes a molten salt reactor assembly, a thermocline unit, phase change heat exchangers, and process heat systems. The thermocline unit includes an insulated tank, an initial inlet, a plurality of zone outlets, and a plurality of gradient zones corresponding to each zone outlet and being stacked in the tank. Each gradient zone has a molten salt portion at a portion temperature corresponding to the molten salt supply from the molten salt reactor being stored in the tank and stratified. The molten salt portions at higher portion temperatures generate thermal energy for process heat systems that require higher temperatures, and molten salt portions at lower portion temperatures generate thermal energy for process heat systems that require lower temperatures. The system continuously pumps the molten salt supply in controlled rates to deliver the heat exchange fluid supply to perform work in the corresponding particular process heat system.
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公开(公告)号:US11205523B2
公开(公告)日:2021-12-21
申请号:US16741307
申请日:2020-01-13
Applicant: TerraPower, LLC
Inventor: Roderick A Hyde , Muriel Y Ishikawa , Clarence T Tegreene , Joshua C Walter , Lowell L Wood, Jr. , Victoria Y. H. Wood
IPC: F28D20/00 , G21D3/00 , F01K3/00 , F01K3/18 , F01K13/02 , F02C1/05 , G21D9/00 , F28D19/00 , F28D17/00
Abstract: A method, system, and apparatus for the thermal storage of nuclear reactor generated energy including diverting a selected portion of energy from a portion of a nuclear reactor system to an auxiliary thermal reservoir and, responsive to a shutdown event, supplying a portion of the diverted selected portion of energy to an energy conversion system of the nuclear reactor system.
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公开(公告)号:US20210053013A1
公开(公告)日:2021-02-25
申请号:US16995528
申请日:2020-08-17
Applicant: Information Systems Laboratories, Inc.
Inventor: Daniel A. Prelewicz , Joseph R. Guerci , Jason G. Williams
IPC: B01D53/78 , B01D53/18 , B01D53/14 , B01D53/62 , C01F11/18 , B01J23/42 , B01J23/72 , B01J23/04 , B01J23/52 , B01J23/46 , B01J21/06 , B01D53/96 , G21D9/00 , G21D3/08
Abstract: A system and method for heat produced at a nuclear power plant as the energy source for carbon dioxide sequestration while simultaneously producing electricity. The system includes a nuclear power plant that differs significantly from conventional designs inasmuch as its design is tightly integrated into the carbon dioxide sequestration system. The system generates electricity and sequesters carbon dioxide at the same time. Instead of simply generating electricity from the nuclear reactor and then using that electricity to run a sequestration process, the method is designed to directly provide the requisite thermal energy to the sequestration process, and simultaneously power an electrical generator. Another feature of the system design is a method of optimizing load balancing between the electrical grid and carbon dioxide sequestration.
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公开(公告)号:US10276269B2
公开(公告)日:2019-04-30
申请号:US15610182
申请日:2017-05-31
Applicant: M. Sheldon Hansen
Inventor: M. Sheldon Hansen
IPC: G21C1/16 , G21C1/22 , G21C3/10 , G21C3/32 , G21C3/54 , G21C5/02 , G21C5/12 , G21C7/00 , G21D9/00 , G21C11/06 , G21C19/14 , G21C19/19 , G21C3/336
Abstract: While the described systems can include any suitable component, in some cases, they include a graphite reactor core defining an internal space that, in some cases, houses one or more fuel wedges, where each wedge defines one or more fuel channels that extend from a first end to a second end of the wedge. In some cases, one or more of the fuel wedges comprise multiple wedge sections that are coupled together end to end and/or in any other suitable manner. In some cases, one or more alignment pins also extend between two sections of a fuel wedge to align the sections. In some cases, one or more seals are also disposed between two sections of a fuel wedge. Thus, in some cases, the reactor core can be relatively long (e.g., to be a pipeline reactor). In some cases, the reactor core is also disposed within a graphite reflector. Other implementations are described.
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公开(公告)号:US20190057783A1
公开(公告)日:2019-02-21
申请号:US16037636
申请日:2018-07-17
Applicant: Terrestrial Energy Inc.
Inventor: David LEBLANC
Abstract: The present relates to the integration of the primary functional elements of graphite moderator and reactor vessel and/or primary heat exchangers and/or control rods into an integral molten salt nuclear reactor (IMSR). Once the design life of the IMSR is reached, for example, in the range of 3 to 10 years, it is disconnected, removed and replaced as a unit. The spent IMSR functions as the medium or long term storage of the radioactive graphite and/or heat exchangers and/or control rods and/or fuel salt contained in the vessel of the IMSR. The present also relates to a nuclear reactor that has a buffer salt surrounding the nuclear vessel. During normal operation of the nuclear reactor, the nuclear reactor operates at a temperature that is lower than the melting point of the buffer salt and the buffer salt acts as a thermal insulator. Upon loss of external cooling, the temperature of the nuclear reactor increases and melts the buffer salt, which can then transfer heat from the nuclear core to a cooled containment vessel.
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公开(公告)号:US10210961B2
公开(公告)日:2019-02-19
申请号:US13469846
申请日:2012-05-11
Applicant: Eric P. Loewen , Jordan E. Hagaman
Inventor: Eric P. Loewen , Jordan E. Hagaman
Abstract: A system and a method for a commercial nuclear repository that turns heat and gamma radiation from spent nuclear fuel into a valuable revenue stream. Gamma radiation from the spent nuclear fuel of the repository may be used to irradiate and sterilize food and other substances. Gamma radiation may also be used to improve the properties of target substances. Additionally, heat decay from the spent nuclear fuel of the repository may be harnessed to heat materials or fluids. The heated fluids may be used, for instance, to produce steam that may make electricity. The heating of working fluids for use in processes, such as heated fluid streams for fermentation or industrial heating, may be transported out of the repository and co-mingled with other heat input, or other fluids.
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公开(公告)号:US09021814B2
公开(公告)日:2015-05-05
申请号:US13322144
申请日:2010-05-20
Applicant: Isabella Lodewina Greeff
Inventor: Isabella Lodewina Greeff
IPC: F02C3/28 , C01B3/36 , B01D53/22 , C01B13/02 , C10G2/00 , C10J3/00 , F02C1/04 , F01K23/06 , G21D9/00
CPC classification number: C01B3/36 , B01D53/229 , B01D2256/12 , B01D2257/102 , C01B13/0251 , C01B2203/0211 , C01B2203/0227 , C01B2203/0233 , C01B2203/0244 , C01B2203/025 , C01B2203/061 , C01B2203/062 , C01B2203/0838 , C01B2203/1241 , C01B2203/84 , C01B2210/0046 , C10G2/32 , C10J3/00 , C10J2300/093 , C10J2300/0959 , C10J2300/0976 , C10J2300/1659 , C10J2300/1678 , C10J2300/1884 , F01K23/068 , F02C1/04 , F02C3/28 , G21D9/00 , Y02E20/18 , Y02P20/129
Abstract: A process for co-producing synthesis gas and power includes producing a synthesis gas comprising at least CO and H2 by reacting a hydrocarbonaceous feedstock with oxygen, the synthesis gas being at a first temperature, separating air from a compressed air stream by means of at least one ion transport membrane unit thereby producing a permeate stream consisting predominantly of oxygen and a reject stream of oxygen-depleted air at a second temperature which is lower than the first temperature, indirectly heating the reject stream of oxygen-depleted air with the synthesis gas and at least partially expanding, the heated reject stream of oxygen-depleted air through at least one turbine to generate power, producing an at least partially expanded reject stream of oxygen-depleted air, and feeding at least a portion of the permeate stream consisting predominantly of oxygen to the synthesis gas generation stage to provide oxygen for production of synthesis gas.
Abstract translation: 共同生产合成气和动力的方法包括通过使烃原料与氧气反应来生产至少包含CO和H 2的合成气,所述合成气处于第一温度,至少通过至少从压缩空气流中分离空气 一个离子传递膜单元,从而在低于第一温度的第二温度下产生主要由氧气和贫氧空气的排出流组成的渗透物流,间接地用合成气加热贫氧空气的废气流,以及 至少部分地膨胀经过至少一个涡轮的加热的贫氧气流,以产生动力,产生至少部分膨胀的贫氧空气的废气流,以及将至少一部分主要由 氧气到合成气生成阶段提供氧气生产合成气。
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