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公开(公告)号：US11149623B2
公开(公告)日：2021-10-19
申请号：US15756872
申请日：2016-09-01
发明人： John Kutsch , David Leblanc
IPC分类号： F01P1/06 , F01D15/08 , G21C15/243 , F04D13/02 , F04D13/04 , F04D29/58 , G21C1/22 , G21C3/54 , F04D7/06 , F01D1/36
摘要： A pneumatic motor assembly that includes a pneumatic motor, which is driven by a compressed gas. The pneumatic motor assembly has a magnet assembly that magnetically couples the pneumatic motor assembly to an implement. After having being used to drive a pneumatic motor, the gas, which has expanded and become colder, cools the magnet assembly The pneumatic motor assembly can thus enable the use to the implement at temperatures at which the magnet assembly would otherwise reach or exceed the maximum operating temperature of the magnet assembly. A flow induction system that includes the pneumatic motor assembly. A method of operating a pneumatic motor assembly that also cools a magnet assembly that is part of the pneumatic motor assembly.
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公开(公告)号：US11200991B2
公开(公告)日：2021-12-14
申请号：US15771742
申请日：2016-10-28
发明人： David Leblanc
摘要： A molten salt nuclear reactor a neutron moderator core that has an inner region that defines channels of a first diameter separated by a first pitch and, an outer region that defines channels of a second diameter separated by a second pitch. The first diameter is larger than the second diameter and the first pitch is larger than the second pitch. This configuration allows for an increased capture of neutrons by fertile elements in the outer region. That is, less neutrons are lost to the outside of the core. The configuration is such that the neutron multiplication factor is larger than one in the inner portion and lower than one in the outer portion.
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公开(公告)号：US11476008B2
公开(公告)日：2022-10-18
申请号：US16037636
申请日：2018-07-17
发明人： David Leblanc
摘要： 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：US11875906B2
公开(公告)日：2024-01-16
申请号：US17950830
申请日：2022-09-22
发明人： David Leblanc
IPC分类号： G21C17/10 , G21C1/22 , G21C1/32 , G21D3/00 , G21D9/00 , G21C5/02 , G21C17/112 , G21C19/28 , G21D1/00
CPC分类号： G21C1/22 , G21C1/322 , G21D3/00 , G21D9/00 , G21C5/02 , G21C17/112 , G21C19/28 , G21D1/00 , Y02E30/30
摘要： 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：US12040098B2
公开(公告)日：2024-07-16
申请号：US17297036
申请日：2019-11-27
摘要： A closed loop heat convection cooling system for nuclear reactors. The cooling system is formed outside the containment structure of the nuclear reactor. The cooling system has cooling assemblies that are housed in protective structures, which shield the cooling assemblies from projectile impact. Air inlet and outlet apertures are formed in the protective structures to cause outside air to be drawn into the protective structures to passively cool the cooling assemblies.
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