公开(公告)号：US20230132031A1

公开(公告)日：2023-04-27

申请号：US17914019

申请日：2021-03-23

申请人： THE RESEARCH FOUNDATION FOR THE STATE UNIVERSITY OF NEW YORK

发明人： Lance Snead ,  Jason Trelewicz

IPC分类号： G21C11/02 ,  C04B35/053 ,  G21F1/08 ,  G21C5/02 ,  G21C5/12

摘要： A composite structure is disclosed comprising a neutron-absorbing metal hydride phase contained within a matrix having a density of greater than 95%. In various embodiments the metal hydride is a hydride of one or more of the following: Gadolinium, Hafnium, Europium, Samarium. The composite structure is utile as a shield for fusion or fission reactors.

公开(公告)号：US11545272B2

公开(公告)日：2023-01-03

申请号：US17427050

申请日：2020-01-31

申请人： Seaborg ApS

发明人： Troels Schönfeldt ,  Jimmy Sølvsteen Nielsen ,  Eirik Eide Pettersen ,  Andreas Vigand Pedersen ,  Daniel John Cooper ,  Ask Emil Løvshall-Jensen

IPC分类号： G21C3/07 ,  G21C3/54 ,  G21C1/22 ,  G21C3/24 ,  G21C5/12

摘要： The present invention relates to a device adapted for producing energy by nuclear fission, the device comprising a core container of a core container material, which core container encloses an inner tubing of an inner tubing material, the inner tubing and/or the core container having an inlet and an outlet, the device further comprising a molten halide salt located in the core container or in the inner tubing, wherein the inner tubing comprises one or more sections consisting of single crystal corundum. The invention further relates to methods of controlling nuclear fission processes using the device and to the use of a corundum tube as a structural material in a nuclear fission device. The invention provides improved economy in molten salt nuclear fission processes.

公开(公告)号：US11476011B2

公开(公告)日：2022-10-18

申请号：US16627738

申请日：2018-12-25

申请人： Joint Stock Company “State Scientific Centre of the Russian Federation—Institute for Physics and Power Engineering named after A.I. Leypunsky” ,  Joint Stock Company «Science and Innovations»

发明人： Nikolay Ivanovich Loginov ,  Aleksandr Sergeevich Mikheev ,  Aleksey Dmitrievich Krotov

IPC分类号： G21C15/257 ,  G21C1/12 ,  G21C5/02 ,  G21C3/40 ,  G21C5/12

摘要： The reactor core includes at least one module, a solid neutron moderator, and a liquid neutron moderators. Each module contains a casing, at least one heat pipe, one fuel element and thermal insulation. The heat pipe comprises a casing, a wick, and a coolant. The fuel element is made of nuclear fuel, arranged along an evaporation area of the heat pipe, around the heat pipe casing, in thermal contact with the heat pipe casing, and enclosed in a can. Liquid metals are used as the coolant of the heat pipe. Thermal insulation is arranged between the can and the module casing. At least one hole is made in the solid neutron moderator. Each module is arranged within a respective hole of the solid neutron moderator. The space between the module casing and the solid neutron moderator is filled with a liquid neutron moderator.

公开(公告)号：US11469005B2

公开(公告)日：2022-10-11

申请号：US16627737

申请日：2018-12-25

申请人： JOINT STOCK COMPANY “STATE SCIENTIFIC CENTRE OF THE RUSSIAN FEDERATION—INSTITUTE FOR PHYSICS AND POWER ENGINEERING NAMED AFTER A.I. LEYPUNSKY” ,  JOINT STOCK COMPANY “SCIENCE AND INNOVATIONS”

发明人： Nikolay Ivanovich Loginov ,  Viktor Viktorovich Litvinov ,  Aleksey Dmitrievich Krotov

IPC分类号： G21C15/257 ,  G21C1/12 ,  G21C5/02 ,  G21C3/322 ,  G21C3/40 ,  G21C5/12

摘要： A nuclear reactor core includes at least one module, a solid neutron moderator, and liquid neutron moderator. Each module comprises a housing, at least one heat pipe, at least one fuel element, casing, and thermal insulation. The heat pipe comprises a housing, wick, and evaporating coolant. The fuel element includes a shell and nuclear fuel. An evaporation zone of the heat pipe and the fuel elements are enclosed by the casing. The casing is filled with a liquid coolant. Liquid metal, for example, lithium, calcium, lead, and/or silver, is used as the heat pipe coolant and the liquid coolant. The thermal insulation is arranged in a space between the casing and module housing. The solid neutron moderator has at least one hole, wherein at least one module is located. A space between the solid neutron moderator and module is filled with the liquid neutron moderator.

公开(公告)号：US11342089B2

公开(公告)日：2022-05-24

申请号：US17024208

申请日：2020-09-17

申请人： Hitachi-GE Nuclear Energy, Ltd.

发明人： Hideyuki Hosokawa ,  Tsuyoshi Ito ,  Hiroko Sukeda ,  Mayu Sasaki ,  Naoshi Usui

IPC分类号： G21D3/00 ,  G06N20/00 ,  G21C17/10 ,  G21D3/10 ,  G21C15/28 ,  G21C1/02 ,  G21C1/08 ,  G21C5/12 ,  G21C17/022

摘要： A reactor water radioactivity concentration of a nuclear power plant can be predicted with high accuracy. First, a plant state quantity prediction value is calculated by using a physical model that describes plant state quantities of the power plant including a flow rate of feedwater and a metal corrosion product concentration in feedwater of the reactor water is calculated. Next, data for supervised learning is created, and the data for supervised learning includes the previously calculated plant state quantity prediction value and a plant state quantity such as the flow rate of feedwater, the metal corrosion product concentration in feedwater, a metal corrosion product concentration in reactor water, and a radioactive metal corrosion concentration of the reactor water in the reactor as input data and includes a radioactive metal corrosion concentration in the reactor water which is an actual measured value as output data, and a predictive model is trained.

公开(公告)号：US11075013B2

公开(公告)日：2021-07-27

申请号：US16690694

申请日：2019-11-21

申请人： TerraPower, LLC

发明人： Ryan Abbott ,  Anselmo T. Cisneros, Jr. ,  Mark R. Werner

IPC分类号： G21C1/32 ,  G21C3/54 ,  G21C5/12 ,  G21C1/04 ,  G21C3/04 ,  G21C5/10 ,  G21C5/16 ,  G21C11/08 ,  G21C1/22

摘要： This disclosure describes various configurations and components of a molten fuel fast or thermal nuclear reactor in which one or more primary heat exchangers are located above the reactor core of the nuclear reactor.

公开(公告)号：US20210222042A1

公开(公告)日：2021-07-22

申请号：US16039770

申请日：2018-07-19

申请人： UT-Battelle, LLC

发明人： Sheng Dai ,  Carter W. Abney ,  Richard T. Mayes ,  Dmitriy Dolzhnikov ,  Huimin Luo

IPC分类号： C09K5/12 ,  G21C5/12 ,  G21C15/28 ,  G21C1/22 ,  G21C3/44

摘要： A heat transfer (exchange) composition comprising a halide salt matrix having dispersed therein nanoparticles comprising elemental carbon in the absence of water and surfactants, wherein said halide is fluoride or chloride, wherein the halide salt may be an alkali halide salt (e.g., lithium fluoride, sodium fluoride, potassium fluoride, rubidium fluoride, sodium chloride, potassium chloride, rubidium chloride, and eutectic mixtures thereof) or an alkaline earth halide salt (e.g., fluoride or chloride salt of beryllium, magnesium, calcium, strontium, or barium), and wherein the nanoparticles comprising elemental carbon may be solid or hollow, and wherein the composition may further include nanoparticles comprising a fissile material (e.g., U, Th, or Pu) dispersed within the composition. Molten salt reactors (MSRs) containing these heat transfer compositions in coolant loops in thermal exchange with a reactor core, as well operation of such MSRs, are also described.

公开(公告)号：US10961160B2

公开(公告)日：2021-03-30

申请号：US14405585

申请日：2014-05-27

申请人： UNIVERSITY OF TSUKUBA ,  DAICO MFG CO., LTD.

发明人： Hiroaki Kumada ,  Tetsuyuki Nakamura ,  Takuji Shigeoka ,  Takeshi Ikeda

IPC分类号： C04B35/64 ,  C04B35/553 ,  C04B35/626 ,  C01F5/28 ,  G21K1/00 ,  G21C5/12

摘要： A fluoride sintered body suitable for a moderator which moderates high-energy neutrons so as to generate neutrons for medical care with which an affected part of the deep part of the body is irradiated to make a tumor extinct comprises MgF2 of a compact polycrystalline structure having a bulk density of 2.90 g/cm3 or more and as regards mechanical strengths, a bending strength of 10 MPa or more and a Vickers hardness of 71 or more.

公开(公告)号：US20210020324A1

公开(公告)日：2021-01-21

申请号：US16722660

申请日：2019-12-20

申请人： Texas Thorium, LLC

发明人： Lin Shao ,  Yassin A. Hassan

IPC分类号： G21G1/08 ,  G21G1/10 ,  G21C3/58 ,  H05H7/22 ,  G21C5/12

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.

公开(公告)号：US20210020323A1

公开(公告)日：2021-01-21

申请号：US16554264

申请日：2019-08-28

申请人： Texas Thorium, LLC

发明人： Lin Shao ,  Yassin A. Hassan

IPC分类号： G21G1/08 ,  G21G1/10 ,  G21C5/12 ,  G21C3/58 ,  H05H7/22

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 being of an energy level sufficient to interact with the salt in the vessel to produce a (p, n) reaction resulting in the generation of a neutron at the first energy level. 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.